Request ID1 Type of the request General request
TargetReaction and processIncident EnergySecondary energy or angleTarget uncertaintyCovariance
 14-SI-28 (n,np) SIG  Threshold-20 MeV 4 pi 20 Y
FieldSubfieldDate Request createdDate Request acceptedOngoing action
 Fusion Material Recycling 21-SEP-05 23-MAR-07 

Requester: Dr Edward T. CHENG at GAT, USA
Email:

Project (context): Structural material for fusion power reactors

Impact:
SiC is a potential very low activation structural material for a fusion power reactor. Al-27 produced from neutron irradiation of Si generates Al-26 via the Al-27(n,2n) reaction. Al-26 is a long-lived radionuclide with a half life of 720,000 years emitting high energy gammas. The concentration of Al-26 in SiC determines whether the decommissioned fusion blanket qualifies for recycling.

Accuracy:
The request for 20% accuracy is based on what seemed feasible for the nuclear data community to achieve and probably would be sufficient for applications as well. It is not based on any sensitivity calculations.

Justification document:
The estimates consider waste generated by four full power years at 5 MW/m2 neutron wall load and are based on a particular scenario for waste handling using evaluations for Si-28(n,x)Al-27 provided by ENDF/B-VI and ADL-3 which are adopted in FENDL/A-2.0. Estimated concentration limits for Si are a factor 10 higher than earlier estimates, so that SiC would qualify as a truly low-activation material. The request asks for experimental data to validate these estimates and a subsequent re-evaluation. No direct experimental data exist.
Reference 1: E.T.Cheng, Jour. Nucl. Mat.,258-263(1998)1767
Reference 2: E.T. Cheng, Proc. of the Int. Conf. on Nuclear Data for Science and Technology, eds. G. Reffo, A. Ventura and C. Grandi, SIF, Bologna, 1158 (1997)

Comment from requester:
Two methods to measure this reaction cross section have been suggested by Herbert Vonach and others. These include (1) Measurement of Na24 activity with high-purity Si samples and intense neutron sources, and (2) Measurement of total production in Si and then subtracting the well known (n,p) cross sections to obtain the (n,n'p) values. An attempt to measure this cross section data at 14 MeV a few years ago failed due to the contamination of the Si samples with the impurity Al. The request for 20% accuracy is based on what seemed feasible for the nuclear data community to achieve and probably would be sufficient for applications as well. It is not based on any sensitivity calculations.

Review comment:

The accuracy is not known. Estimates from present and earlier evaluations differ by a factor of ten.

The request appears to imply application to post-ITER fusion reactors in view of the high neutron dose required to generate relevant quantities of Al-26. Reference [1] refers primarily to the Si-28(n,np) reaction, whereas the production of Al-27 from Si-28 is important. This therefore also implies the (n,d) reaction since the respective thresholds are 12 and 9.7 MeV. Quantitative information is supplied that seems to suggest directly that 20% accuracy is of interest to the application. Stoichiometric SiC has 70 wt% of Si, whereas the scenario assumed for the estimates of Ref. [1] results in an upper limit of 85 wt% Si for recycling. This request qualifies as a General request primarily since the project end time is unspecified.

Entry Status:
Completed (as of SG-C review of May 2018) - Development in state-of-the-art nuclear reaction codes such as TALYS and EMPIRE allowed to fulfil this request. The uncertainties in the main evaluated files (ENDF/B-VIII.0, JEFF-3.3, TENDL-2015) are all consistent above the threshold reaction and vary within a 15-25% band between 13 MeV and 20 MeV.

Main references:
Please report any missing information to hprlinfo@oecd-nea.org

Experiments

Theory/Evaluation

Additional file attached:
Additional file attached:



Request ID2 Type of the request High Priority request
TargetReaction and processIncident EnergySecondary energy or angleTarget uncertaintyCovariance
 8-O-16 (n,a),(n,abs) SIG  2 MeV-20 MeV  See details Y
FieldSubfieldDate Request createdDate Request acceptedOngoing action
 Fission Material recycl, adv. reactors 21-SEP-05 12-SEP-08 Y

Requester: Mr Arnaud COURCELLE at SACLAY, FR
Email: arnaud.courcelle@cea.fr

Project (context): LWR, Material recycling and NEA WPEC Subgroup 26

Impact:
In light water reactors oxygen is present in UOX, MOX and water. The sensitivity coefficient (dk/k)/(dσ/σ)=-3.5 pcm/%. A 30% uncertainty results in an uncertainty for keff of 100 pcm. This important effect was identified by Subgroup 22 of WPEC which investigated the underprediction of the reactivity of light water reactors with the most recent nuclear data evaluations.
A second point concerns helium production which is of importance for the performance of fuel pins and clads. The O-16(n,α) reaction accounts for 25% of the total helium production and contributes 7% to its uncertainty.
A third point concerns the calibration of neutron source strengths using the manganese-sulfate bath technique (NIST). The final requested uncertainty of 1% on neutron source calibrations is very near the 0.5% uncertainty contributed by this reaction.

Design phases of selected reactor and fuel cycle concepts require improved data and methods in order to reduce margins for both economical and safety reasons. A first indicative nuclear data target accuracy assessment was made within WPEC Subgroup 26 (SG-26). The assessment indicated a list of nuclear data priorities for each of the systems considered (ABTR, SFR, EPR, GFR, LFR, ADMAB, VHTR, EPR). These nuclear data priorities should all be addressed to meet target accuracy requirements for the integral parameters characterizing those systems (see the accompanying requests originating from SG-26).

Accuracy:
For (n,a) : 5% in the whole range.
For (n,abs): 9.9 % (2.23 - 6.07 MeV) and 12.1 % (6.07 - 19.6 MeV).

Justification document:
See reference 1 attached: Need for O16(n,alpha) Measurement and Evaluation in the range 2.5 - 10 MeV A. Courcelle et al. (August 2005) and references therein.
See also OECD/NEA WPEC Subgroup 26 Final Report: "Uncertainty and Target Accuracy Assessment for Innovative Systems Using Recent Covariance Data Evaluations" (link to WPEC Subgroup 26 Report in PDF format, 6 Mb), and
And "Nuclear data for improved LEU-LWR reactivity predictions", WPEC Vol. 22 (link to Report).

Comment from requester:
The required accuracy concerns the normalisation of the cross section. A sensitivity analysis is also presented for keff in a fast reactor. Considerable differences exist among evaluations and measurements are discrepant. Recent C-13(α,n) and C-13(α,α) measurements are identified that provide detailed knowledge about the inverse reaction. Together with an R-matrix analysis this may be used to improve the evaluation for the O-16(n,α) reaction. Feedback has been obtained from evaluators at ORNL, LANL and KAPL.

Review comment:

A direct measurement is in preparation using an ionisation chamber with the time projection technique. The measurement aims at providing benchmark data for the R-matrix analysis near the main resonance (En ~ 5 MeV).
A poor resolution measurement should be sufficient to check the normalisation of the R-matrix result, since resonance self-shielding is not an issue.
The recent results for the C-13(α,n) correspond to 4.8-12 MeV neutrons. This covers a part of the region of interest, but not the important range from 2.35 to 4.8 MeV.
The status of the IRMM measurements was presented as a poster in the ND2007 conference, by V. Khriatchkov, G. Giorginis, V. Corcalciuc, M. Kievets, "The cross section of the 16O(n,a)13C reaction in the MeV energy range", contribution 481, ND2007, Nice, April 2007.

The achieved accuracy is estimated to be 30%.

The request is well motivated and the response for follow-up is very encouraging.

Entry Status:
Work in progress (as of SG-C review of May 2018)

Main references:
Please report any missing information to hprlinfo@oecd-nea.org

Experiments

  • G. Giorginis, et al., The cross section of the 16O(n,a)13C reaction in the MeV energy range, ND2007 proceedings, EXFOR 23040
  • V.A. Khryachkov, et al., Study of (n,a) Reaction Cross Section on a Set of Light Nuclei, ISINN-18, Sept. 2011, Dubna, Russia, EXFOR 41575
  • V.A. Khryachkov, et al., (n,a) reaction cross section research at IPPE, CNR*11, EPJ Web of Conferences 21 (2012) 03005, EXFOR 41575
  • S. Harissopulos et al., Cross section of the 13C(a,n)16O reaction: A background for the measurement of geo-neutrinos, PRC 72 (2005) 062801
  • P. Mohr, Revised cross section of the 13C(a,n)16O reaction between 5 and 8 MeV, PRC 97 (2018) 064613; W.A. Peters, Comment on "Cross section of the 13C(a,n)16O reaction: A background for the measurement of geo-neutrinos", PRC 96 (2017) 029801
  • Planned (n,a) measurements at LANL, Demokritos and n_TOF

Theory/Evaluation

  • G. Hale and M. Paris, Status and plans for 1H and 16O evaluations by R-matrix analyses of the N-N and 17O systems, NEMEA-7/CIELO, NEA/NSC/DOC(2014)13, page 13,
  • S. Kunieda, et al., R-matrix Analysis for n +16O Cross-sections up to En = 6.0 MeV with Covariances, NDS 118 (2014) 250-253
  • L. Leal, et al., Resonance parameter and covariance evaluation for 16O up to 6 MeV, EPJ N 2 (2016) 43
  • M.B. Chadwick et al., CIELO Collaboration Summary Results: International Evaluations of Neutron Reactions on Uranium, Plutonium, Iron, Oxygen and Hydrogen, NDS 148 (2018) 189
  • Ongoing evaluation work in the framework of INDEN (CIELO follow-up), see Summary Report of the IAEA CM, 15-17 May 2019, Vienna, Report INDC(NDS)-0788

Validation

Additional file attached:SG26-report.html
Additional file attached:Need for O16(n,alpha).pdf



Request ID5 Type of the request High Priority request
TargetReaction and processIncident EnergySecondary energy or angleTarget uncertaintyCovariance
 72-HF-0 (n,g) SIG  0.5 eV-5.0 keV  4 Y
FieldSubfieldDate Request createdDate Request acceptedOngoing action
 Fission LWR 28-APR-06 16-APR-07 

Requester: Dr Gilles NOGUERE at CAD-DER, FR
Email: gilles.noguere@cea.fr

Project (context): JEFF

Impact:
In nuclear industry hafnium is used as neutron absorbing material to regulate the fission process. Interpretations of critical experiments with UOx fuel conducted by CEA in the AZUR zero-power reactors has shown systematic underestimation of the reactivity worth that may be attributed to an overestimated natural hafnium capture cross section in the epi-thermal energy range [1,2].

Accuracy:
Requested accuracy can be found in the CEA Report "Correlations entre données nucleaires et experiences integrales a plaques, le cas du hafnium", Jean-Marc Palau, CEA-R-5843 (1997). The target accuracy on the effective capture integral has to be lower than 4%

Justification document:
[1] David Bernard, "Determination des incertitudes liés aux grandeurs neutroniques d'interet des reacteurs a eau presurisee a plaques combustibles et application aux etudes de conformite", University Blaise Pascal, Clermont-Ferrand II, France (2001).
[2] G. Noguere, A. Courcelle, J.M. Palau, O.Litaize, "Low neutron energy cross sections of the hafnium isotopes", JEFDOC-1077.pdf, OECD-NEA, Issy-les-Moulineaux, France (2005).
[3] G. Noguere, A. Courcelle, P. Siegler, J.M. Palau, O. Litaize, "Revision of the resolved resonance range of the hafnium isotopes for JEFF-3.1", Technical note CEA Cadarache NT-SPRC/LEPH-05/2001 (2005).

Comment from requester:
Neither the JENDL3.3 nor the JEFF3.1 libraries, that were recently issued, solve the problem. In fact, this was observed for JENDL3.3 before the JEFF3.1 file was constructed. As a result the JEFF3.1 file has been produced with this problem in mind taken into consideration the recent data from Trbovich et al. obtained at RPI [3]. Finally, a 400 pcm underestimation remains that is likely due to interfering isotopic contributions in the resolved energy region. New high resolution measurements appear needed, and would be particularly valuable if they can distinguish the contributions of different isotopes.

Review comment:
Calculations on the AZUR configuration using the JEFF3.1 library give a Hf reactivity worth of about -300 pcm [2].

Entry Status:
Completed (as of SG-C review of May 2018) - The measurements performed at RPI [Trbovich:2009] and JRC-Geel [Ware:2010] allowed to significantly improve the Hf isotopes in JEFF, which now gives satisfactory results for reactivity worth due to Hf data [Noguere:2009].

Main references:
Please report any missing information to hprlinfo@oecd-nea.org

Experiments

  • A.K.M. Meaze et al. (G.N. Kim), Measurement of the Total Neutron Cross-Sections and the Resonance Parameters of Natural Hafnium at the Pohang Neutron Facility, J. Korean Phy. Soc. 46 (2005) 401, EXFOR 31689
  • K. Wisshak, et al., Fast neutron capture on the Hf isotopes: Cross sections, isomer production, and stellar aspects, PRC 73 (2006) 045807, EXFOR 22926
  • M.J. Trbovich, et al., Hafnium resonance parameter analysis using neutron capture and transmission experiments, NSE 161 (2009) 303, EXFOR 14239
  • T. Ware, Measurement and analysis of the resolved resonance cross sections of the natural hafnium isotopes, PhD thesis, University of Birmingham (2010); etheses.bham.ac.uk//id/eprint/807
  • M. Budak, et al., Experimental determination of effective resonance energies for 158Gd(n,g)159Gd and 179Hf(n,g)180mHf reactions, ANE 38 (2011) 2550

Theory/Evaluation

Additional file attached:JEFDOC-1077.ppt
Additional file attached:NT_Hafnium.pdf



Request ID6 Type of the request General request
TargetReaction and processIncident EnergySecondary energy or angleTarget uncertaintyCovariance
 92-U-233 (n,g) SIG  10 keV-1.0 MeV  9 Y
FieldSubfieldDate Request createdDate Request acceptedOngoing action
 Fission Fast reactors 28-APR-06 13-MAR-07 Y

Requester: Dr Gilles NOGUERE at CAD-DER, FR
Email: gilles.noguere@cea.fr

Project (context): JEFF

Impact:
U-233 is the main isotope of relevance to the Th/U fuel cycle. Its most important cross section is the fission cross section. The direct impact of the U-233 capture cross section is rather limited on most reactor related parameters but breeding. However, reliable capture data are needed for the evaluation work.

Accuracy:
The target accuracy on the capture cross section in the unresolved resonance range should be better than 10%

Justification document:
Interpretations of the Profil and Profil-2 experiments [1] performed in the fast reactor Phenix of the CEA Marcoule have shown an underestimation of 9% the U-233 effective capture cross section available in the latest version of the European library JEFF-3.1. The accuracy of the capture data available in EXFOR is not suitable to perform a new evaluation.
References:
[1] J. Tommasi, E. Dupont and P. Marimbeau., "Analysis of Sample Irradiation Experiments in Phénix for JEFF-3.0 Nuclear Data Validation", Nucl. Sci. Eng. 154 (2006) 119-133
[2] J.C.Hopkins and B.C.Diven, "Neutron capture to fission ratios in U-233, U-235, Pu-239", Nucl. Sci. Eng. 12 (1962)169
[3] G. Noguere, E. Dupont, J. Tommasi and D. Bernard, "Nuclear data needs for actinides by comparison with post irradiation experiments", Technical note CEA Cadarache, NT-SPRC/LEPH-05/204 (2005) (see below).

Comment from requester:

Review comment:

Owing to the difficulty in measuring the U-233(n,g) cross section, new evaluation has to take into account the Profil results [3]. Owing to the integral trend given by the interpretation of PROFIL, the final accuracy on the effective capture cross section should be lower than 9%.

Adrien Bidaud, CENBG, Bordeaux, independently investigated the sensitivity of the regeneration of U-233 to various cross sections. Sensitivities were evaluated considering a molten salt reactor under the constraints of criticality and isotopic equilibrium. Large sensitivities are observed for the capture cross section and for nu-bar. He concludes that "Any effort done to confirm the neutron yields and the capture cross section or at least to confirm their uncertainty would be very much appreciated." The energy range of interest is below that of the current request.

Entry Status:
Work in progress (as of SG-C review of May 2018)

Main references:
Please report any missing information to hprlinfo@oecd-nea.org

Experiments

  • C. Carrapico, E. Berthoumieux, et al., Neutron induced capture and fission discrimination using calorimetric shape decomposition, NIM A 704 (2013) 60-67, EXFOR 23071
  • M. Bacak, et al., A compact multi-plate fission chamber for the simultaneous measurement of 233U capture and fission cross-sections, ND2016, EPJ Conferences 146 (2017) 03027

Theory/Evaluation

  • A. Trkov, et al., Evaluated nuclear data for nuclides within the Thorium-Uranium fuel cycle, IAEA Report STI/PUB/1435, 2010

Additional file attached:
Additional file attached:NT-Profil.pdf



Request ID10 Type of the request General request
TargetReaction and processIncident EnergySecondary energy or angleTarget uncertaintyCovariance
 79-AU-197 (n,tot) SIG  5 keV-200 keV  5 
FieldSubfieldDate Request createdDate Request acceptedOngoing action
 Fusion,Science Dosimetry 18-MAY-07 06-JUN-07 

Requester: Dr Roberto CAPOTE NOY at IAEA, AUT
Email: roberto.capotenoy@iaea.org

Project (context): Dosimetry

Impact:
INDC(NDS)-0507 Summary Report of Consultants’ Meeting Review the Requirements to Improve and Extend the IRDF library (International Reactor Dosimetry File (IRDF-2002)), IAEA Headquarters, Vienna, Austria 20-21 April 2006, prepared by L.R. Greenwood and Alan L. Nichols (IAEA, Vienna, January 2007)

Accuracy:
5%

Justification document:
Gold is an extremely important material in nuclear applications: the capture on gold is a standard neutron cross-section, gold has been proposed as a high energy neutron dosimeter (see below), Au-197(n,2n) is a reactor dosimetry reaction considered in all recent IRDF files, etc. Reactions on gold are also of interest for nuclear model code testing as gold is a mono-isotopic element being amenable to detailed calculations.
Taken from INDC(NDS)-0507 "... proposed high energy dosimetry reactions 197Au(n,2n)196Au, 197Au(n,3n)195Au, and 197Au(n,4n)194Au require the extension of the gold evaluation up to 60 MeV"
To our surprise we found large discrepancies in the measured total cross section data of gold in the 5-200 keV energy range (URR) as can be seen from the attached plots. The only existing evaluation (Young et al in red in the figures) has been carried out in the early nineties and has been adopted for all subsequent libraries with minor modifications. This evaluation follows the Seth et al. data measured in 1965, which is in contradiction with several new measurements (for example Purtov 1994 and Wishak 1995-2006). The spread of the Wishak measurements is puzzling.

Comment from requester:
A new dispersive coupled-channel optical model potential (5 keV - 200 MeV) derived using the requested data (plus the existing database above 200 keV) will have a direct impact on future evaluations of neutron induced reactions on gold.

Review comment:
While considerable data exist for the 5-200 keV total cross section, there is considerable scatter in these data. The measurement range is well suited for time-of-flight facilities and may also be accessed with quasi-monoenergetic beams using the Li(p,n) neutron source reactions. For a transmission measurement optimal conditions are obtained with a transmission factor close to 0.5, which implies that getting a sample might be costly, but purity and chemical issues should not be concerns. A measurement which overlaps with the region of the Au capture standard (200 keV to 2.5 MeV) would be of interest to allow a consistency check.

Entry Status:
Completed (as of SG-C review of May 2018) - The JEFF-3.2 evaluation [Sirakov:2013] based on new JRC-Geel measurements [Sirakov:2014;Massimi:2014] is significantly below the target accuracy. The evaluation has been validated against the Grenoble LSDS integral experiment [Zerovnik:2013].

Main references:
Please report any missing information to hprlinfo@oecd-nea.org

Experiments

  • R. Hannaske, et al., Neutron total cross section measurements of gold and tantalum at the nELBE photoneutron source, EPJA 49 (2013) 137, EXFOR 23199
  • I. Sirakov, et al., Results of total cross section measurements for 197Au in the neutron energy region from 4 to 108 keV at GELINA, EPJA 49 (2014) 144, EXFOR 23222
  • C. Massimi et al., Neutron capture cross section measurements for 197Au from 3.5 to 84 keV at GELINA, EPJA 50 (2014) 124, EXFOR 23253

Theory/Evaluation

  • A.B. Smith, Neutron Scattering from the Standard 197Au, ANL/NDM-161, 2005
  • I. Sirakov et al., Evaluation of neutron induced reaction cross sections on gold, Report JRC 78690, EUR 25803, 2013
  • B. Becker, et al., Evaluation of the Covariance Matrix of Estimated Resonance Parameters, NDS 118 (2014) 381
  • A.D. Carlson et al., Evaluation of the Neutron Data Standards, NDS 148 (2018) 143

Validation

Additional file attached:AU197_NTOT_RECENT.ps
Additional file attached:AU197_WISHAK.ps



Request ID13 Type of the request General request
TargetReaction and processIncident EnergySecondary energy or angleTarget uncertaintyCovariance
 24-CR-52 (n,xd),(n,xt) SIG  Threshold-65 MeV  20 Y
FieldSubfieldDate Request createdDate Request acceptedOngoing action
 Fusion IFMIF, First wall 23-OCT-07 07-NOV-07 

Requester: Dr Robin A. FORREST at UKAEA/CUL, UK
Email:

Project (context): JEFF, EFF

Impact:
See attached report EFF/DOC-1015, "Preparatory work for the evaluation of Cr-52 high energy neutron data for EFF", P. Pereslavtsev.

Accuracy:
No experimental data are available for this reaction apart from one point at 14 MeV. Therefore, new experimental results with 20% accuracy are still valuable.

Justification document:
The reactions that need to be considered are Cr-52(n,d+n'p)V-51 and Cr-52(n,t+n'd)V-50. These are important both for modelling and for fusion technology applications. They are discussed in the UKAEA FUS 509 document (Handbook of activation data).

Comment from requester:
Attempts to measure the split in (n,d) and (n,np) to the production of 51V and the split in (n,t), (n,nd) and (n,2np) contributions to the production of 50V would be valuable.

Review comment:

In view of the stable end product both for the (n,d) and (n,nd) reaction, double differential measurements detecting the deuteron are recommended. Such measurements may also provide important additional data for modeling in the form of (n,xp) and (n,xt) double differential cross sections. Measurements with the 'activation-technique' would need to employ a combination of two reactions. Such measurements are complicated, since traces of natural vanadium are a major source of contamination and because the induced activity will be very low. Accelerator Mass Spectrometry is deemed not feasible on account of the background resulting from the wide spread use of vanadium in structural parts. In view of these difficulties it is unlikely that experimentally the cross section for the production of a specific isotope will be accessible. Modeling would have to be invoked.

According to the attached report a single measurement at 14 MeV exists. Above that energy two recent evaluations divergence by nearly a factor 2.

Cr-52 has been under re-evaluation several times in the recent past. For this particular reaction it appears that no progress can be made without new experimental data. In view of the predicted trends in the cross section, it appears that the emphasis of new experimental work should be in the domain above 14 MeV. However, the energy range between threshold (8441 keV) and 14 MeV may be important in an actual fusion reactor.

Entry Status:
Completed (as of SG-C review of May 2018) - This request didn't trigger any measurement and should its priority rise again it will have to be resubmitted. Nevertheless, it has been partially addressed by the JEFF-3.2 evaluation using state-of-the-art nuclear reaction codes [Pereslavtsev:2011].

Main references:
Please report any missing information to hprlinfo@oecd-nea.org

Theory/Evaluation

Additional file attached:effdoc-1015.pdf
Additional file attached:



Request ID14 Type of the request General request
TargetReaction and processIncident EnergySecondary energy or angleTarget uncertaintyCovariance
 94-PU-242 (n,g),(n,tot) SIG  0.5 eV-2.0 keV  8 Y
FieldSubfieldDate Request createdDate Request acceptedOngoing action
 Fission SFR 06-JUL-07 07-NOV-07 Y

Requester: Dr Gilles NOGUERE at CAD-DER, FR
Email: gilles.noguere@cea.fr

Project (context): JEFF

Impact:
G. Aliberti, G. Palmiotti and M. Salvatores, "The role of differential and integral experiments to meet requirements for improved nuclear data", Int. Conf. on Nuclear Data for Science and Technology, Nice, France, 2007.

Accuracy:
Requested accuracy for nuclear applications is widely discussed within the NEA WPEC Subgroup 26, " Nuclear Data Needs for Advanced Reactor Systems". For Pu-242, the requested accuracy on the capture cross section should be lower than 8% in the fast energy range. Interpretations with JEFF-3.1 of the PROFIL and PROFIL-2 experiments carried out in the fast reactor Phenix have shown the overestimation of about 14% of the capture cross section [1,2].

Justification document:
[1] G. Noguere, E. Dupont, J. Tommasi and D. Bernard, "Nuclear data needs for actinides by comparison with post irradiation experiments", Technical note CEA Cadarache, NT-SPRC/LEPH-05/204 (2005).
[2] J. Tommasi, E. Dupont and P. Marimbeau., "Analysis of Sample Irradiation Experiments in Phénix for JEFF-3.0 Nuclear Data Validation", Nucl. Sci. Eng. 154 (2006) 119-133.
[3] E. Rich, G. Noguere, C. De Saint Jean and O. Serot. "Averaged R-Matrix Modelling of the Pu-242 cross sections in the Unresolved Resonance Range", in Proceedings of the Int. Conf. on Nuclear Data for Science and Technology, Nice, France, 2007.

Comment from requester:
To improve the evaluation of the fast energy range in term of average parameters, new high-resolution capture and transmission measurements are needed. The total cross section above 1.5 keV is poorly known. Accurate average radiation width and strength function are required to solve some ambiguous results obtained between optical model calculations and the statistical analysis of the s-wave resonances [3].

Review comment:
NEA WPEC Subgroup-26 will shortly present more detailed requests related to Pu isotopes that are motivated from sensitivity studies of Generation-IV, GNEP and several reference concepts.

Entry Status:
Work in progress (as of SG-C review of May 2018)
Pending new evaluation or validation (as of SG-C review of June 2019)

Main references:
Please report any missing information to hprlinfo@oecd-nea.org

Experiments

  • M.Q. Buckner et al., Absolute measurement of the 242Pu neutron-capture cross section, PRC 93 (2016) 044613, EXFOR 14456
  • J. Lerendegui, et al., Radiative neutron capture on 242Pu in the resonance region at the CERN n_TOF-EAR1 facility, PRC 97 (2018) 024605

Theory/Evaluation

  • M. Herman et al., COMMARA-2.0 Neutron Cross Section Covariance Library, Report BNL-94830-2011, Brookhaven National Laboratory (2011)
  • Pu-242 evaluation was proposed to be part of INDEN (CIELO follow-up) initial program of work (as of Dec. 2017)

Validation

Additional file attached:
Additional file attached:Noguere-Pu242-Note-Technique.pdf



Request ID15 Type of the request High Priority request
TargetReaction and processIncident EnergySecondary energy or angleTarget uncertaintyCovariance
 95-AM-241 (n,g),(n,tot) SIG  Thermal-Fast  See details 
FieldSubfieldDate Request createdDate Request acceptedOngoing action
 Fission LWR, Thermal 08-NOV-07 10-SEP-08 Y

Requester: Dr Osamu IWAMOTO at JAEA, JPN
Email: iwamoto.osamu@jaea.go.jp

Project (context): JENDL and WPEC subgroup 26

Impact:
The thermal value for the total cross section is inconsistent with the best value for the capture cross section. This inconsistency should be removed (JENDL). Current inconsistencies in the measured total cross section for the main low energy resonances should be removed and a capture measurement should be made to demonstrate consistency.

Design phases of selected reactor and fuel cycle concepts require improved data and methods in order to reduce margins for both economical and safety reasons. A first indicative nuclear data target accuracy assessment was made within WPEC Subgroup 26 (SG-26). The assessment indicated a list of nuclear data priorities for each of the systems considered (ABTR, SFR, EPR, GFR, LFR, ADMAB, VHTR, EPR). These nuclear data priorities should all be addressed to meet target accuracy requirements for the integral parameters characterizing those systems (see the accompanying requests originating from SG-26).

Accuracy:
For JENDL: A new measurement with a total uncertainty of 5% for the thermal total cross section would be required to resolve the issue.
For SG-26: Target accuracies are specified per system and per energy group when they are not met by the BOLNA estimate of the current (initial) uncertainties.

Energy RangeUncertainty (%)
  InitialGFR ADMAB
67.4 -183 keV 7 4 2
24.8 -67.4 keV 8 3 2
9.12 -24.8 keV 7 3 2
2.03 -9.12 keV 7 3 2
0.454-2.03 keV 7 3 3

Justification document:
[1] Toru YAMAMOTO, "Analysis of Core Physics Experiments of High Moderation Full MOX LWR", Proc. of the 2005 Symposium on Nuclear Data, February 2-3, 2006, JAEA, Tokai, Japan, pp.7-13, JAEA-Conf 2006-009 (2006). (See attached document)
OECD/NEA WPEC Subgroup 26 Final Report: "Uncertainty and Target Accuracy Assessment for Innovative Systems Using Recent Covariance Data Evaluations" (Link to WPEC Subgroup 26 Report in PDF format, 6 Mb).

Comment from requester:
Given the present state of knowledge the above target accuracies are very tight. However, any attempt that significantly contributes to reducing the present accuracy for this quantity is strongly encouraged. Any such attempt will significantly enhance the accuracy with which reactor integral parameters may be estimated and will therefore impact economic and safety margins.

Review comment:
New experimental work is ongoing at IRMM in collaboration with CEA. Recent capture measurements have taken place at Los Alamos. There appear to be no large discrepancies in thermal capture measurements dating from 2000 as long as it is clearly distinguished whether the isomer contribution is included or not. Sample material available at IRMM is not compatible with an accurate measurement of the total cross section at thermal energy.

Entry Status:
Work in progress (as of SG-C review of May 2018)

Main references:
Please report any missing information to hprlinfo@oecd-nea.org

Experiments

Theory/Evaluation

  • G. Noguere et al., Partial-wave analysis of n+Am-241 reaction cross sections in the resonance region, PRC 92 (2015) 014607
  • K. Mizuyama et al., Correction of the thermal neutron capture cross section of 241Am obtained by the Westcott convention, JNST 54 (2017) 74
  • G. Zerovnik et al., Improving nuclear data accuracy of 241Am and 237Np capture cross sections, EPJ Conferences 146 (2017) 11035
  • H. Harada et al., Improving nuclear data accuracy of the Am-241 capture cross-section, International Evaluation Cooperation, Volume 41, NEA/WPEC-41, report NEA/NSC/R(2020)2, 2020

Additional file attached:Yamamoto_T(MOX-LWR)2006.pdf
Additional file attached:



Request ID18 Type of the request High Priority request
TargetReaction and processIncident EnergySecondary energy or angleTarget uncertaintyCovariance
 92-U-238 (n,inl) SIG  65 keV-20 MeV Emis spec. See details Y
FieldSubfieldDate Request createdDate Request acceptedOngoing action
 Fission Fast Reactors EFR,SFR,ABTR... 28-MAR-08 11-SEP-08 Y

Requester: Prof. Massimo SALVATORES at CADARACHE, FR
Email: massimo.salvatores@cea.fr

Project (context): NEA WPEC Subgroup 26

Impact:
Design phases of selected reactor and fuel cycle concepts require improved data and methods in order to reduce margins for both economical and safety reasons. A first indicative nuclear data target accuracy assessment was made within WPEC Subgroup 26 (SG-26). The assessment indicated a list of nuclear data priorities for each of the systems considered (ABTR, SFR, EPR, GFR, LFR, ADMAB, VHTR, EPR). These nuclear data priorities should all be addressed to meet target accuracy requirements for the integral parameters characterizing those systems (see the accompanying requests originating from SG-26).

The request for improved cross sections and emission spectra and their accuracies for 238U(n,inel) is an important issue that emerges for five of the eight cases studied. The most stringent requirements for this case arise from the GFR and the LFR.
Improvements of the nuclear data for 238U(n,inel) are important for estimates of keff for the GFR, LFR, ABTR and SFR (in order of significance), the peak power of a GFR and the void coefficient of an SFR.

Accuracy:
Target accuracies are specified per system and per energy group when they are not met by the BOLNA estimate of the current (initial) uncertainties.
Energy RangeInitial versus target uncertainties (%)
InitialABTR SFREFRGFRLFR
6.07-19.6 MeV 29 12 7
2.23-6.07 MeV 20 3 5 4 2 3
1.35-2.23 MeV 21 4 5 4 2 2
0.498-1.35 MeV 12 7 6 5 2 2
67.4-183 keV 11 7 9 7 4

Justification document:
OECD/NEA WPEC Subgroup 26 Final Report: "Uncertainty and Target Accuracy Assessment for Innovative Systems Using Recent Covariance Data Evaluations" (Link to WPEC Subgroup 26 Report in PDF format, 6 Mb).

Comment from requester:
Given the present state of knowledge the above target accuracies are very tight. However, any attempt that significantly contributes to reducing the present accuracy for this quantity is strongly encouraged. Any such attempt will significantly enhance the accuracy with which reactor integral parameters may be estimated and will therefore impact economic and safety margins.

Review comment:
See appendix A of the attached report. This request is of high priority.

Entry Status:
Work in progress (as of SG-C review of May 2018)

Main references:
Please report any missing information to hprlinfo@oecd-nea.org

Experiments

Theory/Evaluation

  • A. Santamarina et al., Improvement of 238U Inelastic Scattering Cross Section for an Accurate Calculation of Large Commercial Reactors, ND2013, Nuclear Data Sheets 118 (2014) 118-121
  • R. Capote et al., IAEA CIELO Evaluation of Neutron-induced Reactions on 235U and 238U Targets, NDS 148 (2018) 254

Validation

Additional file attached:SG26-report.html
Additional file attached:



Request ID19 Type of the request High Priority request
TargetReaction and processIncident EnergySecondary energy or angleTarget uncertaintyCovariance
 94-PU-238 (n,f) SIG  9 keV-6 MeV  See details Y
FieldSubfieldDate Request createdDate Request acceptedOngoing action
 Fission Fast Reactors (ADMAB) 31-MAR-08 11-SEP-08 Y

Requester: Prof. Massimo SALVATORES at CADARACHE, FR
Email: massimo.salvatores@cea.fr

Project (context): NEA WPEC Subgroup 26

Impact:
Design phases of selected reactor and fuel cycle concepts require improved data and methods in order to reduce margins for both economical and safety reasons. A first indicative nuclear data target accuracy assessment was made within WPEC Subgroup 26 (SG-26). The assessment indicated a list of nuclear data priorities for each of the systems considered (ABTR, SFR, EPR, GFR, LFR, ADMAB, VHTR, EPR). These nuclear data priorities should all be addressed to meet target accuracy requirements for the integral parameters characterizing those systems (see the accompanying requests originating from SG-26).

The request for the improved cross section and uncertainties for 238Pu(n,f) emerges for five of the eight cases studied. The most stringent requirements for this case arise from the SFR, LFR and ADMAB.
Improvements of the nuclear data for 238Pu(n,f) are important for estimates of keff for the SFR, LFR, ADMAB and GFR (in order of significance), the peak power of ADMAB and the void coefficient of an SFR.

Requested accuracy is required to meet target accuracy for burnup for an Accelerator-Driven Minor Actinides Burner (ADMAB). Details are provided in the SG-26 report: "Uncertainty and Target Accuracy Assessment for Innovative Systems Using Recent Covariance Data Evaluations" (link to WPEC Subgroup 26 Report in PDF format, 6 Mb).

Accuracy:
Target accuracies are specified per system and per energy group when they are not met by the BOLNA estimate of the current (initial) uncertainties.
Energy RangeInitial versus target uncertainties (%)
InitialSFREFRGFRLFRADMAB
2.23 - 6.07 MeV 21 6 7 8 7
1.35 - 2.23 MeV 34 6 24 8 7 6
0.498 - 1.35 MeV 17 3 10 5 3 3
183 - 498 keV 17 4 12 6 3 4
67.4 - 183 keV 9 5 5
24.8 - 67.4 keV 12 6 7 6
9.12 - 24.8 keV 11 7 7 7

Justification document:
OECD/NEA WPEC Subgroup 26 Final Report: "Uncertainty and Target Accuracy Assessment for Innovative Systems Using Recent Covariance Data Evaluations" (link to WPEC Subgroup 26 Report in PDF format, 6 Mb).

Comment from requester:
Given the present state of knowledge the above target accuracies are very tight. However, any attempt that significantly contributes to reducing the present accuracy for this quantity is strongly encouraged. Any such attempt will significantly enhance the accuracy with which reactor integral parameters may be estimated and will therefore impact economic and safety margins.

Review comment:

Entry Status:
Work in progress (as of SG-C review of May 2018)

Main references:
Please report any missing information to hprlinfo@oecd-nea.org

Experiments

Theory/Evaluation

  • M.B. Chadwick et al., ENDF/B-VII.1 Nuclear Data for Science and Technology: Cross Sections, Covariances, Fission Product Yields and Decay Data, p.2937 in NDS 112 (2011) 2887
  • Pu-238 evaluation was proposed to be part of INDEN (CIELO follow-up) initial program of work (as of Dec. 2017)

Validation

Additional file attached:SG26-report.html
Additional file attached:



Request ID21 Type of the request High Priority request
TargetReaction and processIncident EnergySecondary energy or angleTarget uncertaintyCovariance
 95-AM-241 (n,f) SIG  180 keV-20 MeV  See details Y
FieldSubfieldDate Request createdDate Request acceptedOngoing action
 Fission Fast Reactors (ADMAB) 31-MAR-08 11-SEP-08 Y

Requester: Prof. Massimo SALVATORES at CADARACHE, FR
Email: massimo.salvatores@cea.fr

Project (context): NEA WPEC Subgroup 26

Impact:
Design phases of selected reactor and fuel cycle concepts require improved data and methods in order to reduce margins for both economical and safety reasons. A first indicative nuclear data target accuracy assessment was made within WPEC Subgroup 26 (SG-26). The assessment indicated a list of nuclear data priorities for each of the systems considered (ABTR, SFR, EPR, GFR, LFR, ADMAB, VHTR, EPR). These nuclear data priorities should all be addressed to meet target accuracy requirements for the integral parameters characterizing those systems (see the accompanying requests originating from SG-26).

The request for improved cross sections and emission spectra and their accuracies for 241Am(n,f) emerges for four of the eight cases studied. The most stringent requirements for this case arises for the ADMAB, while for the SFR and LFR the needs are nearly met.

Requested accuracy is required to meet target accuracy for keff for Accelerator-Driven Minor Actinides Burner (ADMAB). Details are provided in the OECD/NEA WPEC Subgroup 26 Final Report: "Uncertainty and Target Accuracy Assessment for Innovative Systems Using Recent Covariance Data Evaluations" (link to WPEC Subgroup 26 Report in PDF format, 6 Mb).

Accuracy:
Target accuracies are specified per system and per energy group when they are not met by the BOLNA estimate of the current (initial) uncertainties.

Energy RangeInitial versus target uncertainties (%)
  InitialSFR GFRLFRADMAB
6.07 - 19.6 MeV 13 6
2.23 - 6.07 MeV 12 7 3 2
1.35 - 2.23 MeV 10 6 3 1
0.498 - 1.35 MeV 8 6 3 5 1
183 - 498 keV 8 4

Justification document:
OECD/NEA WPEC Subgroup 26 Final Report: "Uncertainty and Target Accuracy Assessment for Innovative Systems Using Recent Covariance Data Evaluations" (link to WPEC Subgroup 26 Report in PDF format, 6 Mb).

Comment from requester:
SFR: Sodium-cooled Fast Reactor in a TRU burning configuration, i.e., with a Conversion Ratio CR<1
EFR: European Fast Reactor with full recycling of MA and CR~1
GFR: Gas-cooled Fast Reactor also with full recycling of MA
LFR: Lead-cooled Fast Reactor as defined for an IAEA benchmark
ABTR: Advanced Burner Test Reactor Na-cooled core, recently studied within the GNEP initiative
ADMAB: Accelerator-Driven Minor Actinides Burner
PWR: Pressurized Water Reactor

Review comment:
A collaboration between CENBG, IPN-Orsay and CEA have taken data for the reaction 243Am(3He,af) that may yield the fission probability of 242Am. 242Am is the compound nucleus for the 241Am(n,f) reaction. A theoretical estimate of the compound nucleus formation cross section for the latter reaction will than allow to infer the fission cross section. The final accuracy may be sufficient for 2-3 of the four systems.

Entry Status:
Work in progress (as of SG-C review of May 2018)
Pending new evaluation or validation (as of SG-C review of June 2019)

Main references:
Please report any missing information to hprlinfo@oecd-nea.org

Experiments

  • G. Kessedjian et al., Neutron-induced fission cross sections of short-lived actinides with the surrogate reaction method, Phys. Lett. B 692 (2010) 297, EXFOR 23076
  • F. Belloni, et al., Measurement of the neutron-induced fission cross-section of 241Am at the time-of-flight facility n_TOF, EPJ A 49 (2013) 2, EXFOR 23148
  • K. Hirose et al., Simultaneous measurement of neutron-induced fission and capture cross sections for 241Am at neutron energies below fission threshold, NIM A856 (2017) 133, EXFOR 23338
  • New measurement performed at n_TOF EAR2

Theory/Evaluation

  • P. Talou et al., Improved Evaluations of Neutron-Induced Reactions on Americium Isotopes, NSE 155 (2007) 84

Validation

Additional file attached:SG26-report.html
Additional file attached:



Request ID22 Type of the request High Priority request
TargetReaction and processIncident EnergySecondary energy or angleTarget uncertaintyCovariance
 95-AM-242M (n,f) SIG  0.5 keV-6 MeV  See details Y
FieldSubfieldDate Request createdDate Request acceptedOngoing action
 Fission Fast Reactors (SFR) 31-MAR-08 11-SEP-08 Y

Requester: Prof. Massimo SALVATORES at CADARACHE, FR
Email: massimo.salvatores@cea.fr

Project (context): NEA WPEC Subgroup 26

Impact:
Design phases of selected reactor and fuel cycle concepts require improved data and methods in order to reduce margins for both economical and safety reasons. A first indicative nuclear data target accuracy assessment was made within WPEC Subgroup 26 (SG-26). The assessment indicated a list of nuclear data priorities for each of the systems considered (ABTR, SFR, EPR, GFR, LFR, ADMAB, VHTR, EPR). These nuclear data priorities should all be addressed to meet target accuracy requirements for the integral parameters characterizing those systems (see the accompanying requests originating from SG-26).

Requested accuracy is required to meet target accuracy for keff for Sodium-cooled Fast Reactor in a TRU burning configuration, i.e., with a Conversion Ratio CR<1 (SFR). Details are provided in the OECD/NEA WPEC Subgroup 26 Final Report: "Uncertainty and Target Accuracy Assessment for Innovative Systems Using Recent Covariance Data Evaluations" (link to WPEC Subgroup 26 Report in PDF format, 6 Mb).

Accuracy:
Target accuracies are specified per system and per energy group when they are not met by the BOLNA estimate of the current (initial) uncertainties.

Energy RangeInitial versus target uncertainties (%)
  InitialSFR LFRADMAB
2.23 - 6.07 MeV 23 8
1.35 - 2.23 MeV 20 8
0.498- 1.35 MeV 17 4 6
83 - 498 - keV 17 3 8 5
67.4 - 183 - keV 17 3 5
24.8 - 67.4 keV 14 4 6
9.12 - 24.8 keV 12 4 6
2.03 - 9.12 keV 12 7
0.454- 2.03 keV 12 5

Justification document:
OECD/NEA WPEC Subgroup 26 Final Report: "Uncertainty and Target Accuracy Assessment for Innovative Systems Using Recent Covariance Data Evaluations" (link to WPEC Subgroup 26 Report in PDF format, 6 Mb).

Comment from requester:
SFR: Sodium-cooled Fast Reactor in a TRU burning configuration, i.e., with a Conversion Ratio CR<1
EFR: European Fast Reactor with full recycling of MA and CR~1
GFR: Gas-cooled Fast Reactor also with full recycling of MA
LFR: Lead-cooled Fast Reactor as defined for an IAEA benchmark
ABTR: Advanced Burner Test Reactor Na-cooled core, recently studied within the GNEP initiative
ADMAB: Accelerator-Driven Minor Actinides Burner
PWR: Pressurized Water Reactor

Given the present state of knowledge the above target accuracies are very tight. However, any attempt that significantly contributes to reducing the present accuracy for this quantity is strongly encouraged. Any such attempt will significantly enhance the accuracy with which reactor integral parameters may be estimated and will therefore impact economic and safety margins.

Review comment:

Entry Status:
Work in progress (as of SG-C review of May 2018)

Main references:
Please report any missing information to hprlinfo@oecd-nea.org

Experiments

Theory/Evaluation

  • P. Talou et al., Improved Evaluations of Neutron-Induced Reactions on Americium Isotopes, NSE 155 (2007) 84

Validation

Additional file attached:SG26-report.html
Additional file attached:



Request ID25 Type of the request High Priority request
TargetReaction and processIncident EnergySecondary energy or angleTarget uncertaintyCovariance
 96-CM-244 (n,f) SIG  65 keV-6 MeV  See details Y
FieldSubfieldDate Request createdDate Request acceptedOngoing action
 Fission Fast Reactors (ADMAB) 04-APR-08 12-SEP-08 Y

Requester: Prof. Massimo SALVATORES at CADARACHE, FR
Email: massimo.salvatores@cea.fr

Project (context): NEA WPEC Subgroup 26

Impact:
Requested accuracy is required to meet target accuracies for keff, peak power and burnup for the Accelerator-Driven Minor Actinides Burner (ADMAB). Details are provided in the OECD/NEA WPEC Subgroup 26 Final Report: "Uncertainty and Target Accuracy Assessment for Innovative Systems Using Recent Covariance Data Evaluations" (Final Draft attached).

Accuracy:
Target accuracies are specified per system and per energy group when they are not met by the BOLNA estimate of the current (initial) uncertainties.

Energy RangeInitial versus target uncertainties (%)
  InitialSFR EFR GFRLFRADMAB
6.07 - 2.23 MeV 31 8 12 3
2.23 - 1.35 MeV 44 8 13 14 3
1.35 - 0.498 MeV 50 5 20 8 6 2
498 - 183 keV 37 12 4
183 - 67.4 keV 48 7

Justification document:
OECD/NEA WPEC Subgroup 26 Final Report: "Uncertainty and Target Accuracy Assessment for Innovative Systems Using Recent Covariance Data Evaluations" (link to WPEC Subgroup 26 Report in PDF format, 6 Mb).

Comment from requester:
SFR: Sodium-cooled Fast Reactor in a TRU burning configuration, i.e., with a Conversion Ratio CR<1
EFR: European Fast Reactor with full recycling of MA and CR~1
GFR: Gas-cooled Fast Reactor also with full recycling of MA
LFR: Lead-cooled Fast Reactor as defined for an IAEA benchmark
ABTR: Advanced Burner Test Reactor Na-cooled core, recently studied within the GNEP initiative
ADMAB: Accelerator-Driven Minor Actinides Burner
PWR: Pressurized Water Reactor

Review comment:
Experimentally the fission probability of the compound nucleus (245Cm) may be studied in detail through the use of a transfer reaction. The fission cross section for n+244Cm may then be inferred from a theoretical estimate of the compound nucleus formation cross section. Probably, this will be adequate for the EFR and GFR requirements and it could be sufficient for the SFR and LFR, as well.

Entry Status:
Work in progress (as of SG-C review of May 2018)

Main references:
Please report any missing information to hprlinfo@oecd-nea.org

Experiments

  • B.I. Fursov, Fast neutron induced fission cross sections of some minor actinides, ND1997 Proceedings, p.488 (1997), EXFOR 41343

Theory/Evaluation

Validation

Additional file attached:SG26-report.html
Additional file attached:



Request ID27 Type of the request High Priority request
TargetReaction and processIncident EnergySecondary energy or angleTarget uncertaintyCovariance
 96-CM-245 (n,f) SIG  0.5 keV-6 MeV  See details Y
FieldSubfieldDate Request createdDate Request acceptedOngoing action
 Fission Fast Reactors (ADMAB) 04-APR-08 12-SEP-08 Y

Requester: Prof. Massimo SALVATORES at CADARACHE, FR
Email: massimo.salvatores@cea.fr

Project (context): NEA WPEC Subgroup 26

Impact:
Design phases of selected reactor and fuel cycle concepts require improved data and methods in order to reduce margins for both economical and safety reasons. A first indicative nuclear data target accuracy assessment was made within WPEC Subgroup 26 (SG-26). The assessment indicated a list of nuclear data priorities for each of the systems considered (ABTR, SFR, EPR, GFR, LFR, ADMAB, VHTR, EPR). These nuclear data priorities should all be addressed to meet target accuracy requirements for the integral parameters characterizing those systems (see the accompanying requests originating from SG-26).

Requested accuracy is required to meet target accuracies for keff, peak power and burnup for the Accelerator-Driven Minor Actinides Burner (ADMAB). Details are provided in the OECD/NEA WPEC Subgroup 26 Final Report: "Uncertainty and Target Accuracy Assessment for Innovative Systems Using Recent Covariance Data Evaluations" (link to WPEC Subgroup 26 Report in PDF format, 6 Mb).

Accuracy:
Target accuracies are specified per system and per energy group when they are not met by the BOLNA estimate of the current (initial) uncertainties.

Energy RangeInitial versus target uncertainties (%)
InitialSFREFRGFRLFRADMAB
2.23 - 6.07 MeV 31 7
1.35 - 2.23 MeV 44 14 6
0.498 - 1.35 MeV 49 9 43 16 11 3
183 - 498 keV 37 7 13 7 3
67.4 - 183 keV 48 7 42 11 7 3
24.8 - 67.4 keV 27 9 11 9 3
9.12 - 24.8 keV 14 9 3
2.03 - 9.12 keV 13 4
0.454 - 2.03 keV 13 5

Justification document:
OECD/NEA WPEC Subgroup 26 Final Report: "Uncertainty and Target Accuracy Assessment for Innovative Systems Using Recent Covariance Data Evaluations" (link to WPEC Subgroup 26 Report in PDF format, 6 Mb).

Comment from requester:
Given the present state of knowledge the above target accuracies are very tight. However, any attempt that significantly contributes to reducing the present accuracy for this quantity is strongly encouraged. Any such attempt will significantly enhance the accuracy with which reactor integral parameters may be estimated and will therefore impact economic and safety margins.

Review comment:

Entry Status:
Work in progress (as of SG-C review of May 2018)

Main references:
Please report any missing information to hprlinfo@oecd-nea.org

Experiments

Theory/Evaluation

Validation

Additional file attached:SG26-report.html
Additional file attached:



Request ID29 Type of the request High Priority request
TargetReaction and processIncident EnergySecondary energy or angleTarget uncertaintyCovariance
 11-NA-23 (n,inl) SIG  0.5 MeV-1.3 MeV Emis spec. See details Y
FieldSubfieldDate Request createdDate Request acceptedOngoing action
 Fission Fast Reactors (SFR) 04-APR-08 12-SEP-08 Y

Requester: Prof. Massimo SALVATORES at CADARACHE, FR
Email: massimo.salvatores@cea.fr

Project (context): NEA WPEC Subgroup 26

Impact:
Design phases of selected reactor and fuel cycle concepts require improved data and methods in order to reduce margins for both economical and safety reasons. A first indicative nuclear data target accuracy assessment was made within WPEC Subgroup 26 (SG-26). The assessment indicated a list of nuclear data priorities for each of the systems considered (ABTR, SFR, EPR, GFR, LFR, ADMAB, VHTR, EPR). These nuclear data priorities should all be addressed to meet target accuracy requirements for the integral parameters characterizing those systems (see the accompanying requests originating from SG-26).

Requested accuracy is required to meet target accuracy for void coefficient for the Sodium-cooled Fast Reactor in a TRU burning configuration, i.e., with a Conversion Ratio CR<1 (SFR). Details are provided in the OECD/NEA WPEC Subgroup 26 Final Report: "Uncertainty and Target Accuracy Assessment for Innovative Systems Using Recent Covariance Data Evaluations" (link to WPEC Subgroup 26 Report in PDF format, 6 Mb).

Accuracy:
Target accuracies are specified per system and per energy group when they are not met by the BOLNA estimate of the current (initial) uncertainties.

Energy RangeTarget versus initial uncertainties (%)
  InitialABTR SFREFR
1.35 - 2.23 MeV 13 9
0.498 - 1.35 MeV 28 10 4 8

Justification document:
OECD/NEA WPEC Subgroup 26 Final Report: "Uncertainty and Target Accuracy Assessment for Innovative Systems Using Recent Covariance Data Evaluations" (link to WPEC Subgroup 26 Report in PDF format, 6 Mb).

Comment from requester:
Given the present state of knowledge the above target accuracies are very tight. However, any attempt that significantly contributes to reducing the present accuracy for this quantity is strongly encouraged. Any such attempt will significantly enhance the accuracy with which reactor integral parameters may be estimated and will therefore impact economic and safety margins.

Review comment:

Entry Status:
Work in progress (as of SG-C review of May 2018)
Pending new evaluation or validation (as of SG-C review of June 2019)

Main references:
Please report any missing information to hprlinfo@oecd-nea.org

Experiments

Theory/Evaluation

  • S. Kopecky and A. Plompen, R-matrix analysis of the total and inelastic scattering cross sections, EUR 25067 EN (2011)
  • M. Herman et al., COMMARA-2.0 Neutron Cross-Section Covariance Library, Report BNL- 94830-2011, Brookhaven National Laboratory (2011)
  • P. Archier et al., New JEFF-3.2 Sodium Neutron Induced Cross-sections Evaluation for Neutron Fast Reactors Applications: from 0 to 20 MeV, NDS 118 (2014) 140
  • D. Rochman et al., On the evaluation of 23Na neutron-induced reactions and validations, NIM A 612 (2010) 374
  • Ongoing evaluation work in the framework of INDEN (CIELO follow-up), see Summary Report of the IAEA CM, 15-17 May 2019, Vienna, Report INDC(NDS)-0788

Validation

Additional file attached:SG26-report.html
Additional file attached:



Request ID32 Type of the request High Priority request
TargetReaction and processIncident EnergySecondary energy or angleTarget uncertaintyCovariance
 94-PU-239 (n,g) SIG  0.1 eV-1.35 MeV  See details Y
FieldSubfieldDate Request createdDate Request acceptedOngoing action
 Fission Fast Reactors (VHTR) 04-APR-08 12-SEP-08 Y

Requester: Prof. Massimo SALVATORES at CADARACHE, FR
Email: massimo.salvatores@cea.fr

Project (context): NEA WPEC Subgroup 26

Impact:
Design phases of selected reactor and fuel cycle concepts require improved data and methods in order to reduce margins for both economical and safety reasons. A first indicative nuclear data target accuracy assessment was made within WPEC Subgroup 26 (SG-26). The assessment indicated a list of nuclear data priorities for each of the systems considered (ABTR, SFR, EPR, GFR, LFR, ADMAB, VHTR, EPR). These nuclear data priorities should all be addressed to meet target accuracy requirements for the integral parameters characterizing those systems (see the accompanying requests originating from SG-26).

Requested accuracy is required to meet target accuracy for k-eff for all fast reactors and the VHTR. Requirements become more stringent when inelastic cross sections would be allowed less stringent target accuracies (eg for inelastic of 243Am, 238U, but also 239Pu) Details are provided in the OECD/NEA WPEC Subgroup 26 Final Report: "Uncertainty and Target Accuracy Assessment for Innovative Systems Using Recent Covariance Data Evaluations" (link to WPEC Subgroup 26 Report in PDF format, 6 Mb).

Accuracy:
Energy RangeInitial versus target uncertainties (%)
  InitialABTR SFREFRGFRLFRADMABVHTR
   λ=1 λ≠1,a λ≠1,b λ=1 λ≠1,a λ≠1,b λ=1 λ≠1,a λ=1 λ≠1,a λ=1 λ≠1,a λ=1 λ≠1,a λ=1 λ≠1,a
0.498 - 1.35 MeV 18 10 7 5 11 8 7 7 5 7 5 7 5
183 - 498 keV 12 6 4 3 7 5 4 5 4 4 3 5 4
67.4 - 183 keV 9 5 4 3 6 4 4 5 3 6 4 4 3 5 3
24.8 - 67.4 keV 10 6 4 3 7 5 4 5 4 5 4 5 3 5 4
9.12 - 24.8 keV 7 6 4 3 6 4 4 5 3 4 3 5 3 5 3
2.03 - 9.12 keV 16 7 5 4 7 5 4 4 3 3 2 6 4 4 3
0.10 - 0.54 eV 1.4 0.8 0.7

Justification document:
OECD/NEA WPEC Subgroup 26 Final Report: "Uncertainty and Target Accuracy Assessment for Innovative Systems Using Recent Covariance Data Evaluations" (link to WPEC Subgroup 26 Report in PDF format, 6 Mb).

Comment from requester:
Given the present state of knowledge the above target accuracies are very tight. However, any attempt that significantly contributes to reducing the present accuracy for this quantity is strongly encouraged. Any such attempt will significantly enhance the accuracy with which reactor integral parameters may be estimated and will therefore impact economic and safety margins.

Review comment:
See appendix A of the attached report.

Entry Status:
Work in progress (as of SG-C review of May 2018)

Main references:
Please report any missing information to hprlinfo@oecd-nea.org

Experiments

  • S. Mosby et al., Improved neutron capture cross section of Pu-239, PRC 89 (2014) 034610, EXFOR 14383
  • S. Mosby et al., 239Pu(n,g) from 10 eV to 1.3 MeV, NDS 148 (2018) 312
  • S. Mosby et al., Unifying measurement of 239Pu(n,g) in the keV to MeV energy regime, PRC 97 (2018) 041601
  • R. Perez Sanchez et al., Simultaneous Determination of Neutron-Induced Fission and Radiative Capture Cross Sections from Decay Probabilities Obtained with a Surrogate Reaction (to infer the neutron-induced fission and radiative capture cross sections of 239Pu), Phys. Rev. Lett. 125 (2020) 122502

Theory/Evaluation

  • C. De Saint Jean et al., Coordinated Evaluation of Plutonium-239 in the Resonance Region, International Evaluation Cooperation, Volume 34, NEA/WPEC-34, OECD (2014)
  • M.B. Chadwick et al., CIELO Collaboration Summary Results: International Evaluations of Neutron Reactions on Uranium, Plutonium, Iron, Oxygen and Hydrogen, NDS 148 (2018) 189

Validation

Additional file attached:SG26-report.html
Additional file attached:



Request ID33 Type of the request High Priority request
TargetReaction and processIncident EnergySecondary energy or angleTarget uncertaintyCovariance
 94-PU-241 (n,g) SIG  0.1 eV-1.35 MeV  See details Y
FieldSubfieldDate Request createdDate Request acceptedOngoing action
 Fission Fast Reactors (VHTR) 04-APR-08 12-SEP-08 Y

Requester: Prof. Massimo SALVATORES at CADARACHE, FR
Email: massimo.salvatores@cea.fr

Project (context): NEA WPEC Subgroup 26

Impact:
Design phases of selected reactor and fuel cycle concepts require improved data and methods in order to reduce margins for both economical and safety reasons. A first indicative nuclear data target accuracy assessment was made within WPEC Subgroup 26 (SG-26). The assessment indicated a list of nuclear data priorities for each of the systems considered (ABTR, SFR, EPR, GFR, LFR, ADMAB, VHTR, EPR). These nuclear data priorities should all be addressed to meet target accuracy requirements for the integral parameters characterizing those systems (see the accompanying requests originating from SG-26).

Requested accuracy is required to meet target accuracies for keff and burnup for the Very High Temperature Reactor (VHTR). Details are provided in the OECD/NEA WPEC Subgroup 26 Final Report: "Uncertainty and Target Accuracy Assessment for Innovative Systems Using Recent Covariance Data Evaluations" (link to WPEC Subgroup 26 Report in PDF format, 6 Mb).

Accuracy:
Target accuracies are specified per system and per energy group when they are not met by the BOLNA estimate of the current (initial) uncertainties. The weighting factor λ is explained in detail in the accompanying document. Changes from the reference value of λ=1 show the the possible allowance for other target uncertainties. Two cases (A and B) are distinguished for λ≠1 (see Table 24 of the report).

Energy RangeInitial versus target uncertainties (%)
  InitialSFR ADMABVHTRPWR
   λ=1 λ≠1,a λ≠1,b λ=1 λ=1 λ≠1,a λ=1 λ≠1,a
0.498 - 1.35 MeV 32 14 15 13 8
183 - 498 keV 21 11 11 10 7
0.10 - 0.54 eV 7 2 3 3 4

Justification document:
OECD/NEA WPEC Subgroup 26 Final Report: "Uncertainty and Target Accuracy Assessment for Innovative Systems Using Recent Covariance Data Evaluations" (link to WPEC Subgroup 26 Report in PDF format, 6 Mb).

Comment from requester:
Given the present state of knowledge the above target accuracies are very tight. However, any attempt that significantly contributes to reducing the present accuracy for this quantity is strongly encouraged. Any such attempt will significantly enhance the accuracy with which reactor integral parameters may be estimated and will therefore impact economic and safety margins.

Review comment:
See appendix A of the attached report.

Entry Status:
Work in progress (as of SG-C review of May 2018)

Main references:
Please report any missing information to hprlinfo@oecd-nea.org

Theory/Evaluation

  • H. Derrien et al., Reevaluation and Validation of the 241Pu Resonance Parameters in the Energy Range Thermal to 20 eV, NSE 150 (2005) 109
  • Pu-241 evaluation was proposed to be part of INDEN (CIELO follow-up) initial program of work (as of Dec. 2017)

Validation

Additional file attached:SG26-report.html
Additional file attached:



Request ID34 Type of the request High Priority request
TargetReaction and processIncident EnergySecondary energy or angleTarget uncertaintyCovariance
 26-FE-56 (n,inl) SIG  0.5 MeV-20 MeV Emis spec. See details Y
FieldSubfieldDate Request createdDate Request acceptedOngoing action
 Fission ADMAB and SFR 04-APR-08 12-SEP-08 Y

Requester: Prof. Massimo SALVATORES at CADARACHE, FR
Email: massimo.salvatores@cea.fr

Project (context): NEA WPEC Subgroup 26

Impact:
Design phases of selected reactor and fuel cycle concepts require improved data and methods in order to reduce margins for both economical and safety reasons. A first indicative nuclear data target accuracy assessment was made within WPEC Subgroup 26 (SG-26). The assessment indicated a list of nuclear data priorities for each of the systems considered (ABTR, SFR, EPR, GFR, LFR, ADMAB, VHTR, EPR). These nuclear data priorities should all be addressed to meet target accuracy requirements for the integral parameters characterizing those systems (see the accompanying requests originating from SG-26).

Somewhat different requested accuracy is required to meet target accuracies for keff, peak power and void coefficient for the Accelerator-Driven Minor Actinides Burner (ADMAB) and for keff for the Sodium-cooled Fast Reactor in a TRU burning configuration, i.e., with a Conversion Ratio CR<1 (SFR). Details are provided in the OECD/NEA WPEC Subgroup 26 Final Report: "Uncertainty and Target Accuracy Assessment for Innovative Systems Using Recent Covariance Data Evaluations" (link to WPEC Subgroup 26 Report in PDF format, 6 Mb).

Accuracy:
Target accuracies are specified per system and per energy group when they are not met by the BOLNA estimate of the current (initial) uncertainties. The weighting factor λ is explained in detail in the accompanying document. Changes from the reference value of λ=1 show the the possible allowance for other target uncertainties. Two cases (A and B) are distinguished for λ≠1 (see Table 24 of the report).

Energy RangeInitial versus target uncertainties (%)
InitialABTRSFREFRLFRADMAB
λ=1 λ≠1,a λ≠1,b λ=1 λ≠1,a λ≠1,b λ=1 λ≠1,a λ=1 λ≠1,a λ=1 λ≠1,a
6.07 - 19.6 MeV 13 9 11 13
2.23 - 6.07 MeV 7 4 5 7 3 3
1.35 - 2.23 MeV 25 6 7 10 3 4 7 7 7 4 6 2 2
0.498 - 1.35 MeV 16 8 9 13 3 4 6 8 9 4 5 2 2

Justification document:
OECD/NEA WPEC Subgroup 26 Final Report: "Uncertainty and Target Accuracy Assessment for Innovative Systems Using Recent Covariance Data Evaluations" (link to WPEC Subgroup 26 Report in PDF format, 6 Mb).

Comment from requester:
Given the present state of knowledge the above target accuracies are very tight. However, any attempt that significantly contributes to reducing the present accuracy for this quantity is strongly encouraged. Any such attempt will significantly enhance the accuracy with which reactor integral parameters may be estimated and will therefore impact economic and safety margins.

Review comment:
Experimental work was recently completed at IRMM. The impact of the new experimental results is studied at CEA/Cadarache. Uncertainties below 5% will require a major further improvement.

Entry Status:
Work in progress (as of SG-C review of May 2018)

Main references:
Please report any missing information to hprlinfo@oecd-nea.org

Experiments

  • R.O. Nelson et al., Cross-section standards for neutron-induced gamma-ray production in the MeV energy range, ND2004, AIP Conference Proceedings 769 (2004) 838, EXFOR 14118
  • C.M. Castaneda et al., Gamma ray production cross sections from the bombardment of Mg, Al, Si, Ca and Fe with medium energy neutrons, NIM/B 260 (2007) 508, EXFOR 14151
  • Z. Wang et al., Study on coincidence measurement for 56Fe(n,xng) reaction cross section, Atomic Energy Science and Technology 47 (2013) 2177, EXFOR 32720
  • A. Negret et al., Cross-section measurements for the 56Fe(n,xng) reactions, PRC 90 (2014) 034602, EXFOR 23073
  • R. Beyer et al., Inelastic scattering of fast neutrons from excited states in 56Fe, NP A 927 (2014) 41, EXFOR 23134
  • A.M.Daskalakis et al., Quasi-differential elastic and inelastic neutron scattering from iron in the MeV energy range, Annals of Nuclear Energy 110 (2017) 603
  • Ongoing work at University of Kentucky, cf. J.R. Vanhoy et al., Differential Cross Section Measurements at the University of Kentucky -- Adventures in Analysis, NEMEA-7, NEA Report NEA/NSC/DOC(2014)13, p.85
  • related measurement by A. Negret, et al., Cross-section measurements for the 57Fe(n,ng)57Fe and 57Fe(n,2ng)56Fe reactions, PRC 96 (2017) 024620 - See section C which discusses the 847keV gamma production cross section in the 57Fe(n,2n) reaction. This contributes (above En=8-9 MeV) to the 847keV gamma production cross section in natFe(n,n') and therefore may represent a source of uncertainty for the 56Fe(n,inl) measurements performed with natFe targets.
  • related measurement by A. Olacel, et al., Neutron inelastic scattering on 54Fe, Eur. Phys. J. A 54 (2018) 183
  • E. Pirovano, et al., Cross section and neutron angular distribution measurements of neutron scattering on natural iron, PRC 99 (2019) 024601

Theory/Evaluation

Validation

  • C. Jouanne, Sensitivity of the Shielding Benchmarks on Variance-covariance Data for Scattering Angular Distributions, Nuclear Data Sheets 118 (2014) 384
  • I. Kodeli, A. Trkov, G. Zerovnik, Benchmark analysis of iron neutron cross-sections, Jozef Stefan Institute, Ljubljana, Slovenia, Report IJS-DP-11544 (2014)
  • M. Salvatores, et al., Methods and Issues for the Combined Use of Integral Experiments and Covariance Data: Results of a NEA International Collaborative Study, Nuclear Data Sheets 118 (2014) 38
  • G. Palmiotti, et al., Combined Use of Integral Experiments and Covariance Data, Nuclear Data Sheets 118 (2014) 596

Additional file attached:SG26-report.html
Additional file attached:



Request ID35 Type of the request High Priority request
TargetReaction and processIncident EnergySecondary energy or angleTarget uncertaintyCovariance
 94-PU-241 (n,f) SIG  0.5 eV-1.35 MeV  See details Y
FieldSubfieldDate Request createdDate Request acceptedOngoing action
 Fission Fast and Thermal Reactors 04-APR-08 12-SEP-08 Y

Requester: Prof. Massimo SALVATORES at CADARACHE, FR
Email: massimo.salvatores@cea.fr

Project (context): NEA WPEC Subgroup 26

Impact:
Distinct requests for this fission cross section are made at higher energies for fast reactor applications and also at lower energies for thermal reactor applications. Requested accuracy is required to meet target accuracy for k-eff for the GFR, SFR, LFR and ABTR and to meet k-eff and burnup for EFR. Requested accuracy is also required to meet target accuracy for k-eff for the VHTR and k-eff and burnup for the PWR. Details are provided in the OECD/NEA WPEC Subgroup 26 Final Report: "Uncertainty and Target Accuracy Assessment for Innovative Systems Using Recent Covariance Data Evaluations" (Final Draft attached).

Accuracy:
Target accuracies are specified per system and per energy group when they are not met by the BOLNA estimate of the current (initial) uncertainties. The weighting factor λ is explained in detail in the accompanying document. Changes from the reference value of λ=1 show the the possible allowance for other target uncertainties. Two cases (A and B) are distinguished for λ≠1 (see Table 24 of the report).

Energy RangeInitial versus target uncertainties (%)
InitialABTRSFREFRGFRLFRADMABVHTREPR
λ=1 λ≠1,b λ=1 λ≠1,b λ=1 λ≠1,a λ=1 λ=1 λ=1 λ=1 λ≠1,a λ=1 λ≠1,a
0.498 - 1.35 MeV 17 12 9 3 3 8 7 4 4 2
183 - 498 keV 14 9 7 3 2 7 6 3 3 2
67.4 - 183 keV 20 9 7 3 2 6 5 3 3 2
24.8 - 67.4 keV 9 3 3 6 6 3 3 2
9.12 - 24.8 keV 11 4 3 7 6 3 4 2
2.03 - 9.12 keV 10 5 5 8 7 2 5 2
0.454 - 2.03 keV 13 4 4 7 6 3 3
22.6 - 454 eV 19 9 8 5 7 6 8 5 6
0.54 - 4.00 eV 27 9 12 8 10

Justification document:
OECD/NEA WPEC Subgroup 26 Final Report: "Uncertainty and Target Accuracy Assessment for Innovative Systems Using Recent Covariance Data Evaluations" (link to WPEC Subgroup 26 Report in PDF format, 6 Mb).

Comment from requester:
Given the present state of knowledge the above target accuracies are very tight. However, any attempt that significantly contributes to reducing the present accuracy for this quantity is strongly encouraged. Any such attempt will significantly enhance the accuracy with which reactor integral parameters may be estimated and will therefore impact economic and safety margins.

Review comment:
See appendix A of the attached report.

Entry Status:
Work in progress (as of SG-C review of May 2018)

Main references:
Please report any missing information to hprlinfo@oecd-nea.org

Experiments

Theory/Evaluation

  • H. Derrien et al., Reevaluation and Validation of the 241Pu Resonance Parameters in the Energy Range Thermal to 20 eV, NSE 150 (2005) 109
  • Pu-241 evaluation was proposed to be part of INDEN (CIELO follow-up) initial program of work (as of Dec. 2017)

Validation

Additional file attached:SG26-report.html
Additional file attached:



Request ID36 Type of the request High Priority request
TargetReaction and processIncident EnergySecondary energy or angleTarget uncertaintyCovariance
 92-U-238 (n,g) SIG  20 eV-25 keV  See details Y
FieldSubfieldDate Request createdDate Request acceptedOngoing action
 Fission Fast and Thermal Reactors 15-SEP-08 15-SEP-08 

Requester: Prof. Massimo SALVATORES at CADARACHE, FR
Email: massimo.salvatores@cea.fr

Project (context): CEA Cadarache

Impact:
Design phases of selected reactor and fuel cycle concepts require improved data and methods in order to reduce margins for both economical and safety reasons. A first indicative nuclear data target accuracy assessment was made within WPEC Subgroup 26 (SG-26). The assessment indicated a list of nuclear data priorities for each of the systems considered (ABTR, SFR, EPR, GFR, LFR, ADMAB, VHTR, EPR). These nuclear data priorities should all be addressed to meet target accuracy requirements for the integral parameters characterizing those systems (see the accompanying requests originating from SG-26).

Accuracy:
Target accuracies are specified per system and per energy group when they are not met by the BOLNA estimate of the current (initial) uncertainties. The weighting factor λ is explained in detail in the accompanying document. Changes from the reference value of λ=1 show the the possible allowance for other target uncertainties. Two cases (A and B) are distinguished for λ≠1 (see Table 24 of the report).

Energy RangeInitial versus target uncertainties (%)
InitialABTR SFREFRGFRLFRVHTREPR
λ=1 λ≠1,a λ≠1,b λ=1 λ≠1,a λ≠1,b λ=1 λ≠1,a λ=1 λ≠1,a λ=1 λ≠1,a λ=1 λ≠1,a λ=1 λ≠1,a
9.12 - 24.8 keV 9 3 2 2 4 3 3 3 2 2 1 2 2 5 4
2.03 - 9.12 keV 3 1 1
22.6 - 454 eV 2 1 1 1 1

Justification document:
1. OECD/NEA WPEC Subgroup 26 Final Report: "Uncertainty and Target Accuracy Assessment for Innovative Systems Using Recent Covariance Data Evaluations" (link to WPEC Subgroup 26 Report in PDF format, 6 Mb).
2. OECD/NEA WPEC Subgroup 7 (SG-7) Final Report: "Nuclear data standards" (link to WPEC Subgroup 7 Report in PDF format, 450kb).

Comment from requester:
Given the present state of knowledge the above target accuracies are very tight. However, any attempt that significantly contributes to reducing the present accuracy for this quantity is strongly encouraged. Any such attempt will significantly enhance the accuracy with which reactor integral parameters may be estimated and will therefore impact economic and safety margins.

Review comment:
In this particular case high accuracy is required throughout the energy range. Only the groups shown above have initial uncertainties larger than the target uncertainties. The low initial uncertainty is a result of the standards evaluation (see SG-7 report above). Concerns have been raised that despite the excellent efforts of this subgroup an independent check is in order to verify the present view on required corrections to experimental work for the unresolved resonance range.

Entry Status:
Completed (as of SG-C review of May 2018) - New time-of-flight measurements have been performed worldwide, e.g., at LANSCE [Ullmann:2014], JRC-Geel [Kim:2016] and n_TOF [Mingrone:2017;Wright:2017]. These experimental data have been used in the CIELO evaluation [Sirakov:2017,Capote:2018] and for the evaluation of the standards [Carlson:2018]. The CIELO evaluated data have been adopted in ENDF/B-VIII.0 and JEFF-3.3; the evaluated uncertainties match the requested accuracy.

Main references:
Please report any missing information to hprlinfo@oecd-nea.org

Experiments

  • A. Wallner et al., Novel Method to Study Neutron Capture of 235U and 238U Simultaneously at keV Energies, PRL 112 (2014) 192501, EXFOR 23170
  • J.L. Ullmann, et al., Cross section and g-ray spectra for 238U(n,g) measured with the DANCE detector array at the Los Alamos Neutron Science Center, PRC 89 (2014) 034603, EXFOR 14310
  • H.I. Kim et al., Neutron capture cross section measurements for 238U in the resonance region at GELINA, EPJ A 52 (2016) 170, EXFOR 23302
  • F. Mingrone et al., Neutron capture cross section measurement of 238U at the CERN n_TOF facility in the energy region from 1 eV to 700 keV, PRC 95 (2017) 034604, EXFOR 23234
  • T. Wright et al., Measurement of the 238U(n,g) cross section up to 80 keV with the Total Absorption Calorimeter at the CERN n_TOF facility, PRC 96 (2017) 064601

Theory/Evaluation

  • H. Derrien et al., R-Matrix Analysis of 238U High-Resolution Neutron Transmissions and Capture Cross Sections in the Energy Range 0 to 20 keV, NSE 161 (2009) 131
  • R. Dagan et al., Impact of the Doppler Broadened Double Differential Cross Section on Observed Resonance Profiles, ND2013, NDS 118 (2014) 179
  • Kopecky et al., Status of Evaluated Data Files for 238U in the Resonance region, JRC Technical Report, EUR 27504 EN (2015)
  • I. Sirakov et al., Evaluation of cross sections for neutron interactions with 238U in the energy region between 5 keV and 150 keV, EPJ A 53 (2017) 199
  • R. Capote et al., IAEA CIELO Evaluation of Neutron-induced Reactions on 235U and 238U Targets, NDS 148 (2018) 254
  • A.D. Carlson et al., Evaluation of the Neutron Data Standards, NDS 148 (2018) 143

Validation

Additional file attached:SG26-report.html
Additional file attached:



Request ID37 Type of the request High Priority request
TargetReaction and processIncident EnergySecondary energy or angleTarget uncertaintyCovariance
 94-PU-240 (n,f) SIG  0.5 keV-5 MeV  See details Y
FieldSubfieldDate Request createdDate Request acceptedOngoing action
 Fission Fast Reactors 15-SEP-08 15-SEP-08 Y

Requester: Prof. Massimo SALVATORES at CADARACHE, FR
Email: massimo.salvatores@cea.fr

Project (context): CEA Cadarache

Impact:
Design phases of selected reactor and fuel cycle concepts require improved data and methods in order to reduce margins for both economical and safety reasons. A first indicative nuclear data target accuracy assessment was made within WPEC Subgroup 26 (SG-26). The assessment indicated a list of nuclear data priorities for each of the systems considered (ABTR, SFR, EPR, GFR, LFR, ADMAB, VHTR, EPR). These nuclear data priorities should all be addressed to meet target accuracy requirements for the integral parameters characterizing those systems (see the accompanying requests originating from SG-26).

Accuracy:
Target accuracies are specified per system and per energy group when they are not met by the BOLNA estimate of the current (initial) uncertainties. The weighting factor λ is explained in detail in the accompanying document. Changes from the reference value of λ=1 show the the possible allowance for other target uncertainties. Two cases (A and B) are distinguished for λ≠1 (see Table 24 of the report).

Energy RangeInitial versus target uncertainties (%)
InitialSFREFRGFRLFRADMAB
λ=1 λ≠1,a λ≠1,b λ=1 λ≠1,a λ=1 λ≠1,a λ=1 λ≠1,a λ=1 λ≠1,a
2.23 - 6.07 MeV 5 3 3 3 3 3 3 3
1.35 - 2.23 MeV 6 3 3 2 3 3 3 3 3 3
0.498 - 1.35 MeV 6 2 2 2 4 3 2 3 2 2 2 2
0.454 - 2.03 keV 22 13 13 11 9 10

Justification document:
OECD/NEA WPEC Subgroup 26 Final Report: "Uncertainty and Target Accuracy Assessment for Innovative Systems Using Recent Covariance Data Evaluations" (link to WPEC Subgroup 26 Report in PDF format, 6 Mb).

Comment from requester:
Given the present state of knowledge the above target accuracies are very tight. However, any attempt that significantly contributes to reducing the present accuracy for this quantity is strongly encouraged. Any such attempt will significantly enhance the accuracy with which reactor integral parameters may be estimated and will therefore impact economic and safety margins.

Review comment:

Entry Status:
Work in progress (as of SG-C review of May 2018)

Main references:
Please report any missing information to hprlinfo@oecd-nea.org

Experiments

  • A.B. Laptev et al., Int. Conf. on Fission and Properties of Neutron-Rich Nuclei, Sanibel Island, USA, p.462, 2007, EXFOR 41487
  • F. Tovesson et al., Neutron induced fission of 240,242Pu from 1 eV to 200 MeV, PRC 79 (2009) 014613, EXFOR 14223
  • P. Salvador et al., Neutron-induced fission cross section of 240Pu from 0.5 MeV to 3 MeV, PRC 92 (2015) 014620, EXFOR 23281
  • F. Belloni et al., Neutron induced fission cross section measurements of 240Pu and 242Pu, EPJ Conf. 146 (2017) 04062
  • A. Stamatopoulos et al., Investigation of the 240Pu(n,f) reaction at the n_TOF/EAR2 facility in the 9 meV-6 MeV range, PRC 102 (2020) 014616
  • Ongoing work from a JRC-PTB-NPL collaboration and from a CENBG-CEA-JRC collaboration (ANDES and EMRP projects)

Theory/Evaluation

  • D. Brown et al., ENDF/B-VIII.0: The 8th Major Release of the Nuclear Reaction Data Library with CIELO-project Cross Sections, New Standards and Thermal Scattering Data, NDS 148 (2018) 1
  • Pu-240 evaluation was proposed to be part of INDEN (CIELO follow-up) initial program of work (as of Dec. 2017)

Validation

Additional file attached:SG26-report.html
Additional file attached:



Request ID39 Type of the request High Priority request
TargetReaction and processIncident EnergySecondary energy or angleTarget uncertaintyCovariance
 94-PU-242 (n,f) SIG  200 keV-20 MeV  See details Y
FieldSubfieldDate Request createdDate Request acceptedOngoing action
 Fission Fast Reactors 15-SEP-08 15-SEP-08 Y

Requester: Prof. Massimo SALVATORES at CADARACHE, FR
Email: massimo.salvatores@cea.fr

Project (context): CEA Cadarache

Impact:
Design phases of selected reactor and fuel cycle concepts require improved data and methods in order to reduce margins for both economical and safety reasons. A first indicative nuclear data target accuracy assessment was made within WPEC Subgroup 26 (SG-26). The assessment indicated a list of nuclear data priorities for each of the systems considered (ABTR, SFR, EPR, GFR, LFR, ADMAB, VHTR, EPR). These nuclear data priorities should all be addressed to meet target accuracy requirements for the integral parameters characterizing those systems (see the accompanying requests originating from SG-26).

Accuracy:
Target accuracies are specified per system and per energy group when they are not met by the BOLNA estimate of the current (initial) uncertainties. The weighting factor λ is explained in detail in the accompanying document. Changes from the reference value of λ=1 show the the possible allowance for other target uncertainties. Two cases (A and B) are distinguished for λ≠1 (see Table 24 of the report).

Energy RangeInitial versus target uncertainties (%)
InitialSFREFRGFRLFRADMAB
λ=1 λ≠1,b λ=1 λ≠1,a λ=1 λ≠1,a λ=1 λ≠1,a λ=1
6.07 - 19.6 MeV 37 15 14
2.23 - 6.07 MeV 15 5 5 6 6 7 8 7
1.35 - 2.23 MeV 21 5 4 5 6 7 7 5
0.498 - 1.35 MeV 19 4 3 11 9 4 4 4 4 4
183 - 498 keV 19 9 8

Justification document:
OECD/NEA WPEC Subgroup 26 Final Report: "Uncertainty and Target Accuracy Assessment for Innovative Systems Using Recent Covariance Data Evaluations" (link to WPEC Subgroup 26 Report in PDF format, 6 Mb).

Comment from requester:
Given the present state of knowledge the above target accuracies are very tight. However, any attempt that significantly contributes to reducing the present accuracy for this quantity is strongly encouraged. Any such attempt will significantly enhance the accuracy with which reactor integral parameters may be estimated and will therefore impact economic and safety margins.

Review comment:

Entry Status:
Work in progress (as of SG-C review of May 2018)

Main references:
Please report any missing information to hprlinfo@oecd-nea.org

Experiments

Theory/Evaluation

  • M. Herman et al., COMMARA-2.0 Neutron Cross Section Covariance Library, Report BNL-94830-2011, Brookhaven National Laboratory (2011)
  • Pu-242 evaluation was proposed to be part of INDEN (CIELO follow-up) initial program of work (as of Dec. 2017)

Validation

Additional file attached:SG26-report.html
Additional file attached:



Request ID40 Type of the request High Priority request
TargetReaction and processIncident EnergySecondary energy or angleTarget uncertaintyCovariance
 14-SI-28 (n,inl) SIG  1.4 MeV-6 MeV  See details Y
FieldSubfieldDate Request createdDate Request acceptedOngoing action
 Fission Fast Reactors 15-SEP-08 15-SEP-08 

Requester: Prof. Massimo SALVATORES at CADARACHE, FR
Email: massimo.salvatores@cea.fr

Project (context): CEA Cadarache

Impact:
Design phases of selected reactor and fuel cycle concepts require improved data and methods in order to reduce margins for both economical and safety reasons. A first indicative nuclear data target accuracy assessment was made within WPEC Subgroup 26 (SG-26). The assessment indicated a list of nuclear data priorities for each of the systems considered (ABTR, SFR, EPR, GFR, LFR, ADMAB, VHTR, EPR). These nuclear data priorities should all be addressed to meet target accuracy requirements for the integral parameters characterizing those systems (see the accompanying requests originating from SG-26).
This request is specific to the gas-cooled fast reactor.

Accuracy:
Target accuracies are specified per system and per energy group when they are not met by the BOLNA estimate of the current (initial) uncertainties. The weighting factor λ is explained in detail in the accompanying document. Changes from the reference value of λ=1 show the the possible allowance for other target uncertainties. Two cases (A and B) are distinguished for λ≠1 (see Table 24 of the report).

Energy RangeInitial versus target uncertainties (%)
InitialGFR
λ=1 λ≠1,a
2.23 - 6.07 MeV 14 3 4
1.35 - 2.23 MeV 50 6 8

Justification document:
OECD/NEA WPEC Subgroup 26 Final Report: "Uncertainty and Target Accuracy Assessment for Innovative Systems Using Recent Covariance Data Evaluations" (link to WPEC Subgroup 26 Report in PDF format, 6 Mb).

Comment from requester:
Given the present state of knowledge the above target accuracies are very tight. However, any attempt that significantly contributes to reducing the present accuracy for this quantity is strongly encouraged. Any such attempt will significantly enhance the accuracy with which reactor integral parameters may be estimated and will therefore impact economic and safety margins.

Review comment:

Entry Status:
Completed (as of SG-C review of May 2018) - The measurement performed at JRC-Geel [Negret:2013] and the latest evaluations (JEFF-3.3, ENDF/B-VIII.0) all match the requested accuracy.

Main references:
Please report any missing information to hprlinfo@oecd-nea.org

Experiments

  • A. Negret et al., Cross sections for inelastic scattering of neutrons on 28Si and comparison with the 25Mg(a,n)28Si reaction, PRC 88 (2013) 034604, EXFOR 23173
  • A. Negret et al., Neutron inelastic scattering measurements for background assessment in neutrinoless double beta decay experiments, PRC 88 (2014) 027601

Theory/Evaluation

  • M. Herman et al., COMMARA-2.0 Neutron Cross Section Covariance Library, Report BNL-94830-2011, Brookhaven National Laboratory (2011)

Additional file attached:SG26-report.html
Additional file attached:



Request ID41 Type of the request High Priority request
TargetReaction and processIncident EnergySecondary energy or angleTarget uncertaintyCovariance
 82-PB-206 (n,inl) SIG  0.5 MeV-6 MeV  See details Y
FieldSubfieldDate Request createdDate Request acceptedOngoing action
 Fission Fast Reactors 15-SEP-08 15-SEP-08 Y

Requester: Prof. Massimo SALVATORES at CADARACHE, FR
Email: massimo.salvatores@cea.fr

Project (context): CEA Cadarache

Impact:
Design phases of selected reactor and fuel cycle concepts require improved data and methods in order to reduce margins for both economical and safety reasons. A first indicative nuclear data target accuracy assessment was made within WPEC Subgroup 26 (SG-26). The assessment indicated a list of nuclear data priorities for each of the systems considered (ABTR, SFR, EPR, GFR, LFR, ADMAB, VHTR, EPR). These nuclear data priorities should all be addressed to meet target accuracy requirements for the integral parameters characterizing those systems (see the accompanying requests originating from SG-26).
This request is specific to the SFR and ADMAB lead-cooled systems.

Accuracy:
Target accuracies are specified per system and per energy group when they are not met by the BOLNA estimate of the current (initial) uncertainties. The weighting factor λ is explained in detail in the accompanying document. Changes from the reference value of λ=1 show the the possible allowance for other target uncertainties. Two cases (A and B) are distinguished for λ≠1 (see Table 24 of the report).

Energy RangeInitial versus target uncertainties (%)
  InitialLFRADMAB
   λ=1 λ≠1,a λ=1 λ≠1,a
6.07 - 19.6 MeV 18 7 9
2.23 - 6.07 MeV 5 3 4
1.35 - 2.23 MeV 14 5 7
0.498- 1.35 MeV 11 3 4

Justification document:
OECD/NEA WPEC Subgroup 26 Final Report: "Uncertainty and Target Accuracy Assessment for Innovative Systems Using Recent Covariance Data Evaluations" (link to WPEC Subgroup 26 Report in PDF format, 6 Mb).

Comment from requester:
Given the present state of knowledge the above target accuracies are very tight. However, any attempt that significantly contributes to reducing the present accuracy for this quantity is strongly encouraged. Any such attempt will significantly enhance the accuracy with which reactor integral parameters may be estimated and will therefore impact economic and safety margins.

Review comment:
Data have been taken at IRMM for using the (n,n’g)-technique. Experimental results have been included in a new evaluation. The experimental uncertainties are better than 5% in most of the energy range of interest and therefore the request is nearly met. Complementary data for the neutron emission spectrum (angular distribution) would be of interest.

Entry Status:
Pending new evaluation or validation (as of SG-C review of May 2018)

Main references:
Please report any missing information to hprlinfo@oecd-nea.org

Experiments

  • L.C. Mihailescu et al., Neutron (n,xng) cross-section measurements for 52Cr, 209Bi, 206,207,208Pb from threshold up to 20 MeV, PhD thesis, Report EUR 22343 EN, European Communities (2006), EXFOR 23286
  • V.E. Guiseppe et al., Neutron inelastic scattering and reactions in natural Pb as a background in neutrinoless double-beta-decay experiments, PRC 79 (2009) 054604, EXFOR 14231
  • A. Negret, L.C. Mihailescu et al., Cross section measurements for neutron inelastic scattering and the (n, 2n gamma) reaction on 206Pb, PRC 91 (2015) 064618, EXFOR 23292
  • M. Kerveno et al., From gamma emissions to (n,xn) cross sections of interest: The role of GAINS and GRAPhEME in nuclear reaction modeling, EPJA 51 (2015) 167

Theory/Evaluation

  • D. Rochman and A. Koning, Pb and Bi neutron data libraries with full covariance evaluation and improved integral tests, NIM A 589 (2008) 85

Additional file attached:SG26-report.html
Additional file attached:



Request ID42 Type of the request High Priority request
TargetReaction and processIncident EnergySecondary energy or angleTarget uncertaintyCovariance
 82-PB-207 (n,inl) SIG  0.5 MeV-6 MeV  See details Y
FieldSubfieldDate Request createdDate Request acceptedOngoing action
 Fission Fast Reactors 15-SEP-08 15-SEP-08 Y

Requester: Prof. Massimo SALVATORES at CADARACHE, FR
Email: massimo.salvatores@cea.fr

Project (context): CEA Cadarache

Impact:
Design phases of selected reactor and fuel cycle concepts require improved data and methods in order to reduce margins for both economical and safety reasons. A first indicative nuclear data target accuracy assessment was made within WPEC Subgroup 26 (SG-26). The assessment indicated a list of nuclear data priorities for each of the systems considered (ABTR, SFR, EPR, GFR, LFR, ADMAB, VHTR, EPR). These nuclear data priorities should all be addressed to meet target accuracy requirements for the integral parameters characterizing those systems (see the accompanying requests originating from SG-26).
This request is specific to the SFR and ADMAB lead-cooled systems.

Accuracy:
Target accuracies are specified per system and per energy group when they are not met by the BOLNA estimate of the current (initial) uncertainties. The weighting factor λ is explained in detail in the accompanying document. Changes from the reference value of λ=1 show the the possible allowance for other target uncertainties. Two cases (A and B) are distinguished for λ≠1 (see Table 24 of the report).

Energy RangeInitial versus target uncertainties (%)
  InitialLFRADMAB
   λ=1 λ≠1,a λ=1 λ≠1,a
6.07 - 19.6 MeV 18 7 9
2.23 - 6.07 MeV 5 3 4
1.35 - 2.23 MeV 14 5 7
0.498- 1.35 MeV 11 3 4

Justification document:
OECD/NEA WPEC Subgroup 26 Final Report: "Uncertainty and Target Accuracy Assessment for Innovative Systems Using Recent Covariance Data Evaluations" (link to WPEC Subgroup 26 Report in PDF format, 6 Mb).

Comment from requester:
Given the present state of knowledge the above target accuracies are very tight. However, any attempt that significantly contributes to reducing the present accuracy for this quantity is strongly encouraged. Any such attempt will significantly enhance the accuracy with which reactor integral parameters may be estimated and will therefore impact economic and safety margins.

Review comment:
Data have been taken at IRMM for using the (n,n’g)-technique. Experimental results have been included in a new evaluation. The experimental uncertainties are better than 5% in most of the energy range of interest and therefore the request is nearly met. Complementary data for the neutron emission spectrum (angular distribution) would be of interest.

Entry Status:
Pending new evaluation or validation (as of SG-C review of May 2018)

Main references:
Please report any missing information to hprlinfo@oecd-nea.org

Experiments

  • L.C. Mihailescu et al., Neutron (n,xng) cross-section measurements for 52Cr, 209Bi, 206,207,208Pb from threshold up to 20 MeV, PhD thesis, Report EUR 22343 EN, European Communities (2006), EXFOR 23286
  • V.E. Guiseppe et al., Neutron inelastic scattering and reactions in natural Pb as a background in neutrinoless double-beta-decay experiments, PRC 79 (2009) 054604, EXFOR 14231
  • A. Plompen and A. Negret (Eds), Uncertainties and covariances for inelastic scattering data, Report EUR 25208 EN, European Union, 2011
  • M. Kerveno et al., From gamma emissions to (n,xn) cross sections of interest: The role of GAINS and GRAPhEME in nuclear reaction modeling, EPJA 51 (2015) 167

Theory/Evaluation

  • D. Rochman and A. Koning, Pb and Bi neutron data libraries with full covariance evaluation and improved integral tests, NIM A 589 (2008) 85

Additional file attached:SG26-report.html
Additional file attached:



Request ID45 Type of the request High Priority request
TargetReaction and processIncident EnergySecondary energy or angleTarget uncertaintyCovariance
 19-K-39 (n,p),(n,np) SIG  10 MeV-20 MeV  10 Y
FieldSubfieldDate Request createdDate Request acceptedOngoing action
 Fusion  17-MAY-17 11-JUL-17 Y

Requester: Dr Stanislav SIMAKOV at KARLSRUHE, GER
Email: stanislav.simakov@partner.kit.edu

Project (context): IFMIF and DONES material test facilities, and fusion power plants

Impact:
The 39K(n,p) reaction produces 39Ar with decay half-life of 269 years and makes the dominant contribution to the long-lived radioactive inventories in NaK. The latter is considered as a coolant of specimens in the accelerator driven irradiation facilities that are designed now for the fusion material testing (IFMIF [1], DONES [2] ...). Together with the competing reaction 39K(n,np)38Ar they also determine the total amount of Argon gas which impact on the thermal and mechanical properties of sealed specimens containers [3]. The current poor knowledge of these two reactions questions whether NaK could be used in the IFMIF and DONES design. Additionally, since potassium is present in cement and concrete, the 39K(n,p)39Ar reaction impacts on the long-term radioprotection and shielding issues in IFMIF/DONES testing vaults and future fusion power plants.

Accuracy:
The continuous Argon gas leakage through cracks in the welding of sealed containers or their accidental rupture is a complex process. Because of this complexity, the sensitivity analyses quantifying the required accuracy of the cross sections have never been done. However, considering the potentially high impact and the poor knowledge of these cross sections, a request for 10% accuracy is a reasonable requirement that will be practically achievable by utilizing the current techniques. This requirement is supported by the fusion and general nuclear data users.

Justification document:

At 14 MeV neutron energy 3 measurements by proton spectroscopy and activation [4-6] reported 3 times larger value for 39K(n,p)39Ar reaction cross section than measurement by AMS [7]. For competing reaction 39K(n,np)38Ar the situation is vice versa. See Ref. [3] for more information.

The main evaluated libraries are similarly discrepant depending on which experiment they follow.

The new measurement is needed first at 14 MeV to resolve this contradiction.

References

  • [1] F. Arbeiter et al., Nuclear Materials and Energy 9 (2016)59.
  • [2] A. Ibarra et al., Fusion Science and Technology 66 (2014) 252.
  • [3] S.P. Simakov, Y. Qiu, U. Fischer, EFFDOC-1318, JEFF Meeting, OECD, Paris, April 24-27, 2017.
  • [4] M. Bormann et al., Zeitschrift fuer Naturforschung A 15 (1960) 200.
  • [5] D.V. Aleksandrov, L.I. Klochkova, B.S. Kovrigin, Soviet Atomic Energy 39 (1975) 736 (translated from Atomnaya Energiya 39 (1975) 137).
  • [6] W. Schantl, PhD thesis, Institut für Radiumforschung und Kernphysik, University of Vienna, 1970.
  • [7] K.A. Foland, R.J. Borg, M.G. Mustafa, Nuclear Science and Engineering 95 (1987) 128.

Comment from requester:

Review comment:

Entry Status:
Work in progress (as of SG-C review of May 2018)

Main references:
Please report any missing information to hprlinfo@oecd-nea.org

Additional file attached:effdoc-1318.pdf
Additional file attached:



Request ID80 Type of the request Special Purpose Quantity
TargetReaction and processIncident EnergySecondary energy or angleTarget uncertaintyCovariance
 50-SN-117 (n,inl)Sn-117m SIG  5 MeV-10 MeV  2-5 Y
FieldSubfieldDate Request createdDate Request acceptedOngoing action
 Dosimetry Fast fission, D-T fusion 06-OCT-17 06-OCT-17 

Requester: Mr Christophe DESTOUCHES at CAD-DER, FR
Email: christophe.destouches@cea.fr

Project (context): IRDFF project

Impact:
The International Reactor Dosimetry and Fusion File (IRDFF) aims at providing evaluated neutron dosimetry reactions validated for all applications related to fission reactors and fusion technology development [IAEA2017].

Accuracy:
2%-5%

Justification document:
Accurate cross sections as well as spectrum-averaged cross sections (SACS) in relevant and well-characterized neutron fields are essential for improvement and validation of the evaluated data [Simakov2017].

Comment from requester:
The Sn-117(n,n') reaction has by far the lowest reaction threshold and would probe the energy region in the 100 keV range [Destouches2016,2017]. The cross section database is poor. A new evaluation of the cross section is needed, as well as integral measurements in well-characterised neutron fields.

References

  • [IAEA2017] IAEA CRP on Testing and Improving the International Reactor Dosimetry and Fusion File (IRDFF),
    http://www-nds.iaea.org/IRDFFtest/.
  • [Simakov2017] S. Simakov, et al., Proposals for new measurements for IRDFF community and HPRL, September 2017.
  • [Destouches2016] C. Destouches, EPJ Conferences 111, 01002 (2016).
  • [Destouches2017] C. Destouches, et al., The 117Sn(n,n')117mSn reaction: a suitable candidate to investigate the epithermal neutron spectrum by reactor dosimetry techniques, Int. Conf. on Nuclear Energy for New Europe (NENE), Bled, Slovenia, September 11-14, 2017 (NENE 2017 Proceedings).

Review comment:

Entry Status:
Work in progress (as of SG-C review of May 2018)

Main references:
Please report any missing information to hprlinfo@oecd-nea.org

Validation

Additional file attached:Simakov2017.pdf
Additional file attached:Sn117(n,n)Sn117m.pdf



Request ID81 Type of the request Special Purpose Quantity
TargetReaction and processIncident EnergySecondary energy or angleTarget uncertaintyCovariance
 26-FE-0 (n,x)Mn-54 SIG  15 MeV-100 MeV  5-10 Y
FieldSubfieldDate Request createdDate Request acceptedOngoing action
 Dosimetry High-energy 06-OCT-17 06-OCT-17 

Requester: Dr Stanislav SIMAKOV at KARLSRUHE, GER
Email: stanislav.simakov@partner.kit.edu

Project (context): IRDFF project

Impact:
The International Reactor Dosimetry and Fusion File (IRDFF) aims at providing evaluated neutron dosimetry reactions validated for all applications related to fission reactors and fusion technology development [IAEA2017].

Accuracy:
5%-10%

Justification document:
Accurate cross sections as well as spectrum-averaged cross sections (SACS) in relevant and well-characterized neutron fields are essential for improvement and validation of the evaluated data [Simakov2017].

Comment from requester:
The IRDFF project strives to evaluate, and eventually add to the library, high-threshold reactions with cross section plateaus located between 15/20 MeV and 100/150 MeV to meet the requirements of the accelerator-driven high-energy neutron sources. Note that it is important to know the cross section tail up to 100/150 MeV in order to allow the deconvolution of high-energy quasi-monoenergetic neutron source spectra.

References

  • [IAEA2017] IAEA CRP on Testing and Improving the International Reactor Dosimetry and Fusion File (IRDFF),
    http://www-nds.iaea.org/IRDFFtest/.
  • [Simakov2017] S. Simakov, et al., “Proposals for new measurements for IRDFF community and HPRL”, September 2017.

Review comment:

Entry Status:
Work in progress (as of SG-C review of May 2018)

Main references:
Please report any missing information to hprlinfo@oecd-nea.org

Experiments

Theory/Evaluation

Additional file attached:Simakov2017.pdf
Additional file attached:



Request ID82 Type of the request Special Purpose Quantity
TargetReaction and processIncident EnergySecondary energy or angleTarget uncertaintyCovariance
 39-Y-89 (n,p) SIG  15 MeV-100 MeV  5-10 Y
FieldSubfieldDate Request createdDate Request acceptedOngoing action
 Dosimetry High-energy 06-OCT-17 06-OCT-17 

Requester: Dr Stanislav SIMAKOV at KARLSRUHE, GER
Email: stanislav.simakov@partner.kit.edu

Project (context): IRDFF project

Impact:
The International Reactor Dosimetry and Fusion File (IRDFF) aims at providing evaluated neutron dosimetry reactions validated for all applications related to fission reactors and fusion technology development [IAEA2017].

Accuracy:
5%-10%

Justification document:
Accurate cross sections as well as spectrum-averaged cross sections (SACS) in relevant and well-characterized neutron fields are essential for improvement and validation of the evaluated data [Simakov2017].

Comment from requester:
The IRDFF project strives to evaluate, and eventually add to the library, high-threshold reactions with cross section plateaus located between 15/20 MeV and 100/150 MeV to meet the requirements of the accelerator-driven high-energy neutron sources. Note that it is important to know the cross section tail up to 100/150 MeV in order to allow the deconvolution of high-energy quasi-monoenergetic neutron source spectra.

References

  • [IAEA2017] IAEA CRP on Testing and Improving the International Reactor Dosimetry and Fusion File (IRDFF),
    http://www-nds.iaea.org/IRDFFtest/.
  • [Simakov2017] S. Simakov, et al., “Proposals for new measurements for IRDFF community and HPRL”, September 2017.

Review comment:

Entry Status:
Work in progress (as of SG-C review of May 2018)

Main references:
Please report any missing information to hprlinfo@oecd-nea.org

Additional file attached:Simakov2017.pdf
Additional file attached:Y89(n,xn).pdf



Request ID83 Type of the request Special Purpose Quantity
TargetReaction and processIncident EnergySecondary energy or angleTarget uncertaintyCovariance
 39-Y-89 (n,xn) x=2-4 SIG  15MeV/Thr.-100 MeV  5-10 Y
FieldSubfieldDate Request createdDate Request acceptedOngoing action
 Dosimetry High-energy 06-OCT-17 06-OCT-17 

Requester: Dr Stanislav SIMAKOV at KARLSRUHE, GER
Email: stanislav.simakov@partner.kit.edu

Project (context): IRDFF project

Impact:
The International Reactor Dosimetry and Fusion File (IRDFF) aims at providing evaluated neutron dosimetry reactions validated for all applications related to fission reactors and fusion technology development [IAEA2017].

Accuracy:
5%-10%

Justification document:
Accurate cross sections as well as spectrum-averaged cross sections (SACS) in relevant and well-characterized neutron fields are essential for improvement and validation of the evaluated data [Simakov2017].

Comment from requester:
The IRDFF project strives to evaluate, and eventually add to the library, high-threshold reactions with cross section plateaus located between 15/20 MeV and 100/150 MeV to meet the requirements of the accelerator-driven high-energy neutron sources. Note that it is important to know the cross section tail up to 100/150 MeV in order to allow the deconvolution of high-energy quasi-monoenergetic neutron source spectra.

References

  • [IAEA2017] IAEA CRP on Testing and Improving the International Reactor Dosimetry and Fusion File (IRDFF),
    http://www-nds.iaea.org/IRDFFtest/.
  • [Simakov2017] S. Simakov, et al., “Proposals for new measurements for IRDFF community and HPRL”, September 2017.

Review comment:

Entry Status:
Work in progress (as of SG-C review of May 2018)

Main references:
Please report any missing information to hprlinfo@oecd-nea.org

Experiments

Theory/Evaluation

Additional file attached:Simakov2017.pdf
Additional file attached:Y89(n,xn).pdf



Request ID84 Type of the request Special Purpose Quantity
TargetReaction and processIncident EnergySecondary energy or angleTarget uncertaintyCovariance
 22-TI-0 (n,x)Sc-46 SIG  15 MeV-100 MeV  5-10 Y
FieldSubfieldDate Request createdDate Request acceptedOngoing action
 Dosimetry High-energy 06-OCT-17 06-OCT-17 

Requester: Dr Stanislav SIMAKOV at KARLSRUHE, GER
Email: stanislav.simakov@partner.kit.edu

Project (context): IRDFF project

Impact:
The International Reactor Dosimetry and Fusion File (IRDFF) aims at providing evaluated neutron dosimetry reactions validated for all applications related to fission reactors and fusion technology development [IAEA2017].

Accuracy:
5%-10%

Justification document:
Accurate cross sections as well as spectrum-averaged cross sections (SACS) in relevant and well-characterized neutron fields are essential for improvement and validation of the evaluated data [Simakov2017].

Comment from requester:
The IRDFF project strives to evaluate, and eventually add to the library, high-threshold reactions with cross section plateaus located between 15/20 MeV and 100/150 MeV to meet the requirements of the accelerator-driven high-energy neutron sources. Note that it is important to know the cross section tail up to 100/150 MeV in order to allow the deconvolution of high-energy quasi-monoenergetic neutron source spectra.

References

  • [IAEA2017] IAEA CRP on Testing and Improving the International Reactor Dosimetry and Fusion File (IRDFF),
    http://www-nds.iaea.org/IRDFFtest/.
  • [Simakov2017] S. Simakov, et al., “Proposals for new measurements for IRDFF community and HPRL”, September 2017.

Review comment:

Entry Status:
Work in progress (as of SG-C review of May 2018)

Main references:
Please report any missing information to hprlinfo@oecd-nea.org

Theory/Evaluation

Additional file attached:Simakov2017.pdf
Additional file attached:



Request ID85 Type of the request Special Purpose Quantity
TargetReaction and processIncident EnergySecondary energy or angleTarget uncertaintyCovariance
 22-TI-0 (n,x)Sc-47 SIG  15 MeV-100 MeV  5-10 Y
FieldSubfieldDate Request createdDate Request acceptedOngoing action
 Dosimetry High-energy 06-OCT-17 06-OCT-17 

Requester: Dr Stanislav SIMAKOV at KARLSRUHE, GER
Email: stanislav.simakov@partner.kit.edu

Project (context): IRDFF project

Impact:
The International Reactor Dosimetry and Fusion File (IRDFF) aims at providing evaluated neutron dosimetry reactions validated for all applications related to fission reactors and fusion technology development [IAEA2017].

Accuracy:
5%-10%

Justification document:
Accurate cross sections as well as spectrum-averaged cross sections (SACS) in relevant and well-characterized neutron fields are essential for improvement and validation of the evaluated data [Simakov2017].

Comment from requester:
The IRDFF project strives to evaluate, and eventually add to the library, high-threshold reactions with cross section plateaus located between 15/20 MeV and 100/150 MeV to meet the requirements of the accelerator-driven high-energy neutron sources. Note that it is important to know the cross section tail up to 100/150 MeV in order to allow the deconvolution of high-energy quasi-monoenergetic neutron source spectra.

References

  • [IAEA2017] IAEA CRP on Testing and Improving the International Reactor Dosimetry and Fusion File (IRDFF),
    http://www-nds.iaea.org/IRDFFtest/.
  • [Simakov2017] S. Simakov, et al., “Proposals for new measurements for IRDFF community and HPRL”, September 2017.

Review comment:

Entry Status:
Work in progress (as of SG-C review of May 2018)

Main references:
Please report any missing information to hprlinfo@oecd-nea.org

Theory/Evaluation

Additional file attached:Simakov2017.pdf
Additional file attached:



Request ID86 Type of the request Special Purpose Quantity
TargetReaction and processIncident EnergySecondary energy or angleTarget uncertaintyCovariance
 22-TI-0 (n,x)Sc-48 SIG  15 MeV-100 MeV  5-10 Y
FieldSubfieldDate Request createdDate Request acceptedOngoing action
 Dosimetry High-energy 06-OCT-17 06-OCT-17 

Requester: Dr Stanislav SIMAKOV at KARLSRUHE, GER
Email: stanislav.simakov@partner.kit.edu

Project (context): IRDFF project

Impact:
The International Reactor Dosimetry and Fusion File (IRDFF) aims at providing evaluated neutron dosimetry reactions validated for all applications related to fission reactors and fusion technology development [IAEA2017].

Accuracy:
5%-10%

Justification document:
Accurate cross sections as well as spectrum-averaged cross sections (SACS) in relevant and well-characterized neutron fields are essential for improvement and validation of the evaluated data [Simakov2017].

Comment from requester:
The IRDFF project strives to evaluate, and eventually add to the library, high-threshold reactions with cross section plateaus located between 15/20 MeV and 100/150 MeV to meet the requirements of the accelerator-driven high-energy neutron sources. Note that it is important to know the cross section tail up to 100/150 MeV in order to allow the deconvolution of high-energy quasi-monoenergetic neutron source spectra.

References

  • [IAEA2017] IAEA CRP on Testing and Improving the International Reactor Dosimetry and Fusion File (IRDFF),
    http://www-nds.iaea.org/IRDFFtest/.
  • [Simakov2017] S. Simakov, et al., “Proposals for new measurements for IRDFF community and HPRL”, September 2017.

Review comment:

Entry Status:
Work in progress (as of SG-C review of May 2018)

Main references:
Please report any missing information to hprlinfo@oecd-nea.org

Theory/Evaluation

Additional file attached:Simakov2017.pdf
Additional file attached:



Request ID87 Type of the request Special Purpose Quantity
TargetReaction and processIncident EnergySecondary energy or angleTarget uncertaintyCovariance
 71-LU-175 (n,xn) x=2-4 SIG  15MeV/Thr.-100 MeV  5-10 Y
FieldSubfieldDate Request createdDate Request acceptedOngoing action
 Dosimetry High-energy 06-OCT-17 06-OCT-17 

Requester: Dr Stanislav SIMAKOV at KARLSRUHE, GER
Email: stanislav.simakov@partner.kit.edu

Project (context): IRDFF project

Impact:
The International Reactor Dosimetry and Fusion File (IRDFF) aims at providing evaluated neutron dosimetry reactions validated for all applications related to fission reactors and fusion technology development [IAEA2017].

Accuracy:
5%-10%

Justification document:
Accurate cross sections as well as spectrum-averaged cross sections (SACS) in relevant and well-characterized neutron fields are essential for improvement and validation of the evaluated data [Simakov2017].

Comment from requester:
The IRDFF project strives to evaluate, and eventually add to the library, high-threshold reactions with cross section plateaus located between 15/20 MeV and 100/150 MeV to meet the requirements of the accelerator-driven high-energy neutron sources. Note that it is important to know the cross section tail up to 100/150 MeV in order to allow the deconvolution of high-energy quasi-monoenergetic neutron source spectra.

References

  • [IAEA2017] IAEA CRP on Testing and Improving the International Reactor Dosimetry and Fusion File (IRDFF),
    http://www-nds.iaea.org/IRDFFtest/.
  • [Simakov2017] S. Simakov, et al., “Proposals for new measurements for IRDFF community and HPRL”, September 2017.

Review comment:

Entry Status:
Work in progress (as of SG-C review of May 2018)

Main references:
Please report any missing information to hprlinfo@oecd-nea.org

Additional file attached:Simakov2017.pdf
Additional file attached:Lu(n,xn).pdf



Request ID88 Type of the request Special Purpose Quantity
TargetReaction and processIncident EnergySecondary energy or angleTarget uncertaintyCovariance
 41-NB-93 (n,xn) x=2-4 SIG  15MeV/Thr.-100 MeV  5-10 Y
FieldSubfieldDate Request createdDate Request acceptedOngoing action
 Dosimetry High-energy 06-OCT-17 06-OCT-17 

Requester: Dr Stanislav SIMAKOV at KARLSRUHE, GER
Email: stanislav.simakov@partner.kit.edu

Project (context): IRDFF project

Impact:
The International Reactor Dosimetry and Fusion File (IRDFF) aims at providing evaluated neutron dosimetry reactions validated for all applications related to fission reactors and fusion technology development [IAEA2017].

Accuracy:
5%-10%

Justification document:
Accurate cross sections as well as spectrum-averaged cross sections (SACS) in relevant and well-characterized neutron fields are essential for improvement and validation of the evaluated data [Simakov2017].

Comment from requester:
The IRDFF project strives to evaluate, and eventually add to the library, high-threshold reactions with cross section plateaus located between 15/20 MeV and 100/150 MeV to meet the requirements of the accelerator-driven high-energy neutron sources. Note that it is important to know the cross section tail up to 100/150 MeV in order to allow the deconvolution of high-energy quasi-monoenergetic neutron source spectra.
The present request concerns the following reactions:
Nb-93(n,2n)Nb-92m
Nb-93(n,3n)Nb-91m
Nb-93(n,4n)Nb-90

References

  • [IAEA2017] IAEA CRP on Testing and Improving the International Reactor Dosimetry and Fusion File (IRDFF),
    http://www-nds.iaea.org/IRDFFtest/.
  • [Simakov2017] S. Simakov, et al., “Proposals for new measurements for IRDFF community and HPRL”, September 2017.

Review comment:

Entry Status:
Work in progress (as of SG-C review of May 2018)

Main references:
Please report any missing information to hprlinfo@oecd-nea.org

Experiments

  • M. Majerle, P. Bem, et al., Au, Bi, Co and Nb cross-section measured by quasimonoenergetic neutrons from p+7Li reaction in the energy range of 18-36 MeV, Nuclear Physics A 953 (2016) 139

Theory/Evaluation

Additional file attached:Simakov2017.pdf
Additional file attached:Nb(n,xn).pdf



Request ID89 Type of the request Special Purpose Quantity
TargetReaction and processIncident EnergySecondary energy or angleTarget uncertaintyCovariance
 29-CU-63 (n,2n) SIG  20 MeV-100 MeV  5-10 Y
FieldSubfieldDate Request createdDate Request acceptedOngoing action
 Dosimetry High-energy 06-OCT-17 06-OCT-17 

Requester: Dr Stanislav SIMAKOV at KARLSRUHE, GER
Email: stanislav.simakov@partner.kit.edu

Project (context): IRDFF project

Impact:
The International Reactor Dosimetry and Fusion File (IRDFF) aims at providing evaluated neutron dosimetry reactions validated for all applications related to fission reactors and fusion technology development [IAEA2017].

Accuracy:
5%-10%

Justification document:
Accurate cross sections as well as spectrum-averaged cross sections (SACS) in relevant and well-characterized neutron fields are essential for improvement and validation of the evaluated data [Simakov2017].

Comment from requester:
The IRDFF project strives to evaluate, and eventually add to the library, high-threshold reactions with cross section plateaus located between 15/20 MeV and 100/150 MeV to meet the requirements of the accelerator-driven high-energy neutron sources. Note that it is important to know the cross section tail up to 100/150 MeV in order to allow the deconvolution of high-energy quasi-monoenergetic neutron source spectra.

References

  • [IAEA2017] IAEA CRP on Testing and Improving the International Reactor Dosimetry and Fusion File (IRDFF),
    http://www-nds.iaea.org/IRDFFtest/.
  • [Simakov2017] S. Simakov, et al., “Proposals for new measurements for IRDFF community and HPRL”, September 2017.

Review comment:

Entry Status:
Work in progress (as of SG-C review of May 2018)

Main references:
Please report any missing information to hprlinfo@oecd-nea.org

Theory/Evaluation

Additional file attached:Simakov2017.pdf
Additional file attached:



Request ID90 Type of the request Special Purpose Quantity
TargetReaction and processIncident EnergySecondary energy or angleTarget uncertaintyCovariance
 26-FE-54 (n,2n) SIG  15 MeV-100 MeV  5-10 Y
FieldSubfieldDate Request createdDate Request acceptedOngoing action
 Dosimetry High-energy 06-OCT-17 06-OCT-17 

Requester: Dr Stanislav SIMAKOV at KARLSRUHE, GER
Email: stanislav.simakov@partner.kit.edu

Project (context): IRDFF project

Impact:
The International Reactor Dosimetry and Fusion File (IRDFF) aims at providing evaluated neutron dosimetry reactions validated for all applications related to fission reactors and fusion technology development [IAEA2017].

Accuracy:
5%-10%

Justification document:
Accurate cross sections as well as spectrum-averaged cross sections (SACS) in relevant and well-characterized neutron fields are essential for improvement and validation of the evaluated data [Simakov2017].

Comment from requester:
The IRDFF project strives to evaluate, and eventually add to the library, high-threshold reactions with cross section plateaus located between 15/20 MeV and 100/150 MeV to meet the requirements of the accelerator-driven high-energy neutron sources. Note that it is important to know the cross section tail up to 100/150 MeV in order to allow the deconvolution of high-energy quasi-monoenergetic neutron source spectra.

References

  • [IAEA2017] IAEA CRP on Testing and Improving the International Reactor Dosimetry and Fusion File (IRDFF),
    http://www-nds.iaea.org/IRDFFtest/.
  • [Simakov2017] S. Simakov, et al., “Proposals for new measurements for IRDFF community and HPRL”, September 2017.

Review comment:

Entry Status:
Work in progress (as of SG-C review of May 2018)

Main references:
Please report any missing information to hprlinfo@oecd-nea.org

Experiments

Theory/Evaluation

Additional file attached:Simakov2017.pdf
Additional file attached:Fe54n2n.pdf



Request ID91 Type of the request Special Purpose Quantity
TargetReaction and processIncident EnergySecondary energy or angleTarget uncertaintyCovariance
 79-AU-197 (n,xn) x=3-5 SIG  20MeV/Thr.-100 MeV  5-10 Y
FieldSubfieldDate Request createdDate Request acceptedOngoing action
 Dosimetry High-energy 06-OCT-17 06-OCT-17 

Requester: Dr Stanislav SIMAKOV at KARLSRUHE, GER
Email: stanislav.simakov@partner.kit.edu

Project (context): IRDFF project

Impact:
The International Reactor Dosimetry and Fusion File (IRDFF) aims at providing evaluated neutron dosimetry reactions validated for all applications related to fission reactors and fusion technology development [IAEA2017].

Accuracy:
5%-10%

Justification document:
Accurate cross sections as well as spectrum-averaged cross sections (SACS) in relevant and well-characterized neutron fields are essential for improvement and validation of the evaluated data [Simakov2017].

Comment from requester:
The IRDFF project strives to evaluate, and eventually add to the library, high-threshold reactions with cross section plateaus located between 15/20 MeV and 100/150 MeV to meet the requirements of the accelerator-driven high-energy neutron sources. Note that it is important to know the cross section tail up to 100/150 MeV in order to allow the deconvolution of high-energy quasi-monoenergetic neutron source spectra.

References

  • [IAEA2017] IAEA CRP on Testing and Improving the International Reactor Dosimetry and Fusion File (IRDFF),
    http://www-nds.iaea.org/IRDFFtest/.
  • [Simakov2017] S. Simakov, et al., “Proposals for new measurements for IRDFF community and HPRL”, September 2017.

Review comment:

Entry Status:
Work in progress (as of SG-C review of May 2018)

Main references:
Please report any missing information to hprlinfo@oecd-nea.org

Experiments

Additional file attached:Simakov2017.pdf
Additional file attached:Au(n,xn)_HighEnDos.pdf



Request ID92 Type of the request Special Purpose Quantity
TargetReaction and processIncident EnergySecondary energy or angleTarget uncertaintyCovariance
 69-TM-169 (n,xn) x=2-3 SIG  15 MeV-100 MeV  5-10 Y
FieldSubfieldDate Request createdDate Request acceptedOngoing action
 Dosimetry High-energy 06-OCT-17 06-OCT-17 

Requester: Dr Stanislav SIMAKOV at KARLSRUHE, GER
Email: stanislav.simakov@partner.kit.edu

Project (context): IRDFF project

Impact:
The International Reactor Dosimetry and Fusion File (IRDFF) aims at providing evaluated neutron dosimetry reactions validated for all applications related to fission reactors and fusion technology development [IAEA2017].

Accuracy:
5%-10%

Justification document:
Accurate cross sections as well as spectrum-averaged cross sections (SACS) in relevant and well-characterized neutron fields are essential for improvement and validation of the evaluated data [Simakov2017].

Comment from requester:
The IRDFF project strives to evaluate, and eventually add to the library, high-threshold reactions with cross section plateaus located between 15/20 MeV and 100/150 MeV to meet the requirements of the accelerator-driven high-energy neutron sources. Note that it is important to know the cross section tail up to 100/150 MeV in order to allow the deconvolution of high-energy quasi-monoenergetic neutron source spectra.

References

  • [IAEA2017] IAEA CRP on Testing and Improving the International Reactor Dosimetry and Fusion File (IRDFF),
    http://www-nds.iaea.org/IRDFFtest/.
  • [Simakov2017] S. Simakov, et al., “Proposals for new measurements for IRDFF community and HPRL”, September 2017.

Review comment:

Entry Status:
Work in progress (as of SG-C review of May 2018)

Main references:
Please report any missing information to hprlinfo@oecd-nea.org

Experiments

Theory/Evaluation

Additional file attached:Simakov2017.pdf
Additional file attached:Tm(n,xn).pdf



Request ID93 Type of the request Special Purpose Quantity
TargetReaction and processIncident EnergySecondary energy or angleTarget uncertaintyCovariance
 83-BI-209 (n,xn) x=3-10 SIG  20MeV/Thr.-150 MeV  5-10 Y
FieldSubfieldDate Request createdDate Request acceptedOngoing action
 Dosimetry High-energy 06-OCT-17 06-OCT-17 

Requester: Dr Stanislav SIMAKOV at KARLSRUHE, GER
Email: stanislav.simakov@partner.kit.edu

Project (context): IRDFF project

Impact:
The International Reactor Dosimetry and Fusion File (IRDFF) aims at providing evaluated neutron dosimetry reactions validated for all applications related to fission reactors and fusion technology development [IAEA2017].

Accuracy:
5%-10%

Justification document:
Accurate cross sections as well as spectrum-averaged cross sections (SACS) in relevant and well-characterized neutron fields are essential for improvement and validation of the evaluated data [Simakov2017].

Comment from requester:
The IRDFF project strives to evaluate, and eventually add to the library, high-threshold reactions with cross section plateaus located between 15/20 MeV and 100/150 MeV to meet the requirements of the accelerator-driven high-energy neutron sources. Note that it is important to know the cross section tail up to 100/150 MeV in order to allow the deconvolution of high-energy quasi-monoenergetic neutron source spectra.

References

  • [IAEA2017] IAEA CRP on Testing and Improving the International Reactor Dosimetry and Fusion File (IRDFF),
    http://www-nds.iaea.org/IRDFFtest/.
  • [Simakov2017] S. Simakov, et al., “Proposals for new measurements for IRDFF community and HPRL”, September 2017.

Review comment:

Entry Status:
Work in progress (as of SG-C review of May 2018)

Main references:
Please report any missing information to hprlinfo@oecd-nea.org

Experiments

Theory/Evaluation

Additional file attached:Simakov2017.pdf
Additional file attached:Bi(n,xn)_HighEnDos.pdf



Request ID94 Type of the request Special Purpose Quantity
TargetReaction and processIncident EnergySecondary energy or angleTarget uncertaintyCovariance
 27-CO-59 (n,xn) x=3-5 SIG  20MeV/Thr.-150 MeV  5-10 Y
FieldSubfieldDate Request createdDate Request acceptedOngoing action
 Dosimetry High-energy 06-OCT-17 06-OCT-17 

Requester: Dr Stanislav SIMAKOV at KARLSRUHE, GER
Email: stanislav.simakov@partner.kit.edu

Project (context): IRDFF project

Impact:
The International Reactor Dosimetry and Fusion File (IRDFF) aims at providing evaluated neutron dosimetry reactions validated for all applications related to fission reactors and fusion technology development [IAEA2017].

Accuracy:
5%-10%

Justification document:
Accurate cross sections as well as spectrum-averaged cross sections (SACS) in relevant and well-characterized neutron fields are essential for improvement and validation of the evaluated data [Simakov2017].

Comment from requester:
The IRDFF project strives to evaluate, and eventually add to the library, high-threshold reactions with cross section plateaus located between 15/20 MeV and 100/150 MeV to meet the requirements of the accelerator-driven high-energy neutron sources. Note that it is important to know the cross section tail up to 100/150 MeV in order to allow the deconvolution of high-energy quasi-monoenergetic neutron source spectra.

References

  • [IAEA2017] IAEA CRP on Testing and Improving the International Reactor Dosimetry and Fusion File (IRDFF),
    http://www-nds.iaea.org/IRDFFtest/.
  • [Simakov2017] S. Simakov, et al., “Proposals for new measurements for IRDFF community and HPRL”, September 2017.

Review comment:

Entry Status:
Work in progress (as of SG-C review of May 2018)

Main references:
Please report any missing information to hprlinfo@oecd-nea.org

Experiments

  • M. Majerle, P. Bem, et al., Au, Bi, Co and Nb cross-section measured by quasimonoenergetic neutrons from p+7Li reaction in the energy range of 18-36 MeV, Nuclear Physics A 953 (2016) 139
  • M. Majerle, et al., Experimental Validation of IRDFF Cross-Sections in Quasi-MonoEnergetic Neutron Fluxes in 20-35 MeV Energy Range, IAEA report INDC(NDS)-0789, May 2019

Theory/Evaluation

Additional file attached:Simakov2017.pdf
Additional file attached:Co(n,xn).pdf



Request ID95 Type of the request Special Purpose Quantity
TargetReaction and processIncident EnergySecondary energy or angleTarget uncertaintyCovariance
 45-RH-103 (n,xn) x=4-8 SIG  Threshold-150 MeV  5-10 Y
FieldSubfieldDate Request createdDate Request acceptedOngoing action
 Dosimetry High-energy 06-OCT-17 06-OCT-17 

Requester: Dr Stanislav SIMAKOV at KARLSRUHE, GER
Email: stanislav.simakov@partner.kit.edu

Project (context): IRDFF project

Impact:
The International Reactor Dosimetry and Fusion File (IRDFF) aims at providing evaluated neutron dosimetry reactions validated for all applications related to fission reactors and fusion technology development [IAEA2017].

Accuracy:
5%-10%

Justification document:
Accurate cross sections as well as spectrum-averaged cross sections (SACS) in relevant and well-characterized neutron fields are essential for improvement and validation of the evaluated data [Simakov2017].

Comment from requester:
The IRDFF project strives to evaluate, and eventually add to the library, high-threshold reactions with cross section plateaus located between 15/20 MeV and 100/150 MeV to meet the requirements of the accelerator-driven high-energy neutron sources. Note that it is important to know the cross section tail up to 100/150 MeV in order to allow the deconvolution of high-energy quasi-monoenergetic neutron source spectra.

References

  • [IAEA2017] IAEA CRP on Testing and Improving the International Reactor Dosimetry and Fusion File (IRDFF),
    http://www-nds.iaea.org/IRDFFtest/.
  • [Simakov2017] S. Simakov, et al., “Proposals for new measurements for IRDFF community and HPRL”, September 2017.

Review comment:

Entry Status:
Work in progress (as of SG-C review of May 2018)

Main references:
Please report any missing information to hprlinfo@oecd-nea.org

Additional file attached:Simakov2017.pdf
Additional file attached:Pronyaev-nxn-high-en-dos.pdf



Request ID96 Type of the request Special Purpose Quantity
TargetReaction and processIncident EnergySecondary energy or angleTarget uncertaintyCovariance
 57-LA-139 (n,xn) x=4-10 SIG  Threshold-150 MeV  5-10 Y
FieldSubfieldDate Request createdDate Request acceptedOngoing action
 Dosimetry High-energy 06-OCT-17 06-OCT-17 

Requester: Dr Stanislav SIMAKOV at KARLSRUHE, GER
Email: stanislav.simakov@partner.kit.edu

Project (context): IRDFF project

Impact:
The International Reactor Dosimetry and Fusion File (IRDFF) aims at providing evaluated neutron dosimetry reactions validated for all applications related to fission reactors and fusion technology development [IAEA2017].

Accuracy:
5%-10%

Justification document:
Accurate cross sections as well as spectrum-averaged cross sections (SACS) in relevant and well-characterized neutron fields are essential for improvement and validation of the evaluated data [Simakov2017].

Comment from requester:
The IRDFF project strives to evaluate, and eventually add to the library, high-threshold reactions with cross section plateaus located between 15/20 MeV and 100/150 MeV to meet the requirements of the accelerator-driven high-energy neutron sources. Note that it is important to know the cross section tail up to 100/150 MeV in order to allow the deconvolution of high-energy quasi-monoenergetic neutron source spectra.

References

  • [IAEA2017] IAEA CRP on Testing and Improving the International Reactor Dosimetry and Fusion File (IRDFF),
    http://www-nds.iaea.org/IRDFFtest/.
  • [Simakov2017] S. Simakov, et al., “Proposals for new measurements for IRDFF community and HPRL”, September 2017.

Review comment:

Entry Status:
Work in progress (as of SG-C review of May 2018)

Main references:
Please report any missing information to hprlinfo@oecd-nea.org

Additional file attached:Simakov2017.pdf
Additional file attached:Pronyaev-nxn-high-en-dos.pdf



Request ID97 Type of the request High Priority request
TargetReaction and processIncident EnergySecondary energy or angleTarget uncertaintyCovariance
 24-CR-50 (n,g) SIG  1 keV-100 keV  8-10 Y
FieldSubfieldDate Request createdDate Request acceptedOngoing action
 Fission  20-JAN-18 05-FEB-18 Y

Requester: Dr Roberto CAPOTE NOY at IAEA, AUT
Email: roberto.capotenoy@iaea.org

Project (context):

Impact:

Neutron absorption in the Cr isotopes of structural materials affects the criticality of fast reactor assemblies [Koscheev2017]. These cross sections are also of interest for stellar nucleosynthesis [Kadonis10].

Accuracy:

8-10% in average cross-sections and calculated MACS at 10, 30, 100 keV.

Selected criticality benchmarks with large amounts of Cr (e.g., PU-MET-INTER-002, and HEU-COMP-INTER-005/4=KBR-15/Cr) show large criticality changes of the order of 1000 pcm due to 30% change in Cr-53 capture in the region from 1 keV up to 100 keV [Trkov2018]. On the other side different evaluations (e.g., BROND-3.1, ENDF/B-VII.1, ENDF/B-VIII.0 and JEFF-3.3) for Cr-53(n,g) are discrepant by 30% in the same energy region. For Cr-50, evaluated files show better agreement at those energies but they are lower than Mughabghab evaluation of the resonance integral by 35%. These discrepancies are not reflected in estimated uncertainty of the evaluated files (e.g., JEFF-3.3 uncertainty is around 10% which is inconsistent with the observed spread in evaluations). Due to these differences we request new capture data with 8-10% uncertainty to discriminate between different evaluations and improve the C/E for benchmarks containing Chromium and/or SS.

Justification document:

Criticality benchmarks can test different components of stainless steel (SS), including Cr which is a large component of some SS. Currently, a large part of the uncertainty in SS capture seems to be driven by uncertainty in Cr capture [Koscheev2017]. Indeed, some benchmarks highly sensitive to Cr (as a component of SS) indicate a need for much higher capture in Cr for both Pu and U fueled critical assemblies (e.g., HEU-COMP-INTER-005/4=KBR-15/Cr and PU-MET-INTER-002=ZPR-6/10).

Capture in natural Cr is driven by capture on Cr-50 and especially in odd Cr-53.

For Cr-53(n,g) there is a very large spread in MACS(30) values in different libraries compared to recommended KADoNiS 1.0 [Kadonis10] value of 41 +/- 10 mb (the latter is 25% larger). Existing measurements from the 70s are even larger being close to 60 mb with 30% uncertainty.

Note also discrepancies in resonance integrals (in barns) between evaluated libraries and ATLAS [Mughabghab2006] for both Cr-50(n,g) and Cr-53(n,g)

ReactionENDF/B-VII.1BROND-3.1ATLAS 2006
Cr-50(n,g)7.217.2111.7 +/- 0.2
Cr-53(n,g)8.4211.212.3

Finally, the re-evaluation for ENDF/B-VIII.0 of the ORNL TOF measurement on enriched Cr-53 target [Guber2011] contradicts the increase suggested in Ref. [Koscheev2017] where preliminary data have been used.

Such contradictions need to be resolved thanks to new measurements and evaluation.

References

  • [Guber2011] K.H. Guber, et al., Journal of the Korean Physical Society 59(2), 1685-1688, 2011
  • [Kadonis10] KADoNiS 1.0 (http://exp-astro.physik.uni-frankfurt.de/kadonis1.0)
  • [Koscheev2017] V. Koscheev, et al., EPJ Conf. 146, 06025, 2017
  • [Mughabghab2006] S.F. Mughabghab, Atlas of Neutron Resonances, 5th Edition, Elsevier, 2006
  • [Trkov2018] A. Trkov, O. Cabellos and R. Capote, Sensitivity of selected benchmarks to Cr-53 and Cr-50 capture, January 2018

Comment from requester:

- Cr-50(n,g) may be measured by activation or TOF. An accurate activation measurement at 5 and 25 keV may help in solving the puzzle of Cr capture.
- Cr-53(n,g) can only be measured by TOF. There is no publication of the final analysis of the ORNL TOF measurement using enriched Cr-53 sample.
- Lead Slowing Down Spectrometer (LSDS) measurements of Cr-50, Cr-53 and Cr-52 enriched samples and of Cr-nat sample could be extremely important to validate and select a proper evaluation of Cr capture cross section below 100 keV. These measurements are strongly encouraged as complementary to TOF and feasible activation measurements.

Review comment:

Entry Status:
Work in progress (as of SG-C review of May 2018)

Main references:
Please report any missing information to hprlinfo@oecd-nea.org

Experiments

Theory/Evaluation

Validation

  • V. Koscheev et al., Use the results of measurements on KBR facility for testing of neutron data of main structural materials for fast reactors, EPJ Conferences 146 (2007) 06025

Additional file attached:Trkov2018.pdf
Additional file attached:



Request ID98 Type of the request High Priority request
TargetReaction and processIncident EnergySecondary energy or angleTarget uncertaintyCovariance
 24-CR-53 (n,g) SIG  1 keV-100 keV  8-10 Y
FieldSubfieldDate Request createdDate Request acceptedOngoing action
 Fission  20-JAN-18 05-FEB-18 Y

Requester: Dr Roberto CAPOTE NOY at IAEA, AUT
Email: roberto.capotenoy@iaea.org

Project (context):

Impact:

Neutron absorption in the Cr isotopes of structural materials affects the criticality of fast reactor assemblies [Koscheev2017]. These cross sections are also of interest for stellar nucleosynthesis [Kadonis10].

Accuracy:

8-10% in average cross-sections and calculated MACS at 10, 30, 100 keV.

Selected criticality benchmarks with large amounts of Cr (e.g., PU-MET-INTER-002, and HEU-COMP-INTER-005/4=KBR-15/Cr) show large criticality changes of the order of 1000 pcm due to 30% change in Cr-53 capture in the region from 1 keV up to 100 keV [Trkov2018]. On the other side different evaluations (e.g., BROND-3.1, ENDF/B-VII.1, ENDF/B-VIII.0 and JEFF-3.3) for Cr-53(n,g) are discrepant by 30% in the same energy region. For Cr-50, evaluated files show better agreement at those energies but they are lower than Mughabghab evaluation of the resonance integral by 35%. These discrepancies are not reflected in estimated uncertainty of the evaluated files (e.g., JEFF-3.3 uncertainty is around 10% which is inconsistent with the observed spread in evaluations). Due to these differences we request new capture data with 8-10% uncertainty to discriminate between different evaluations and improve the C/E for benchmarks containing Chromium and/or SS.

Justification document:

Criticality benchmarks can test different components of stainless steel (SS), including Cr which is a large component of some SS. Currently, a large part of the uncertainty in SS capture seems to be driven by uncertainty in Cr capture [Koscheev2017]. Indeed, some benchmarks highly sensitive to Cr (as a component of SS) indicate a need for much higher capture in Cr for both Pu and U fueled critical assemblies (e.g., HEU-COMP-INTER-005/4=KBR-15/Cr and PU-MET-INTER-002=ZPR-6/10).

Capture in natural Cr is driven by capture on Cr-50 and especially in odd Cr-53.

For Cr-53(n,g) there is a very large spread in MACS(30) values in different libraries compared to recommended KADoNiS 1.0 [Kadonis10] value of 41 +/- 10 mb (the latter is 25% larger). Existing measurements from the 70s are even larger being close to 60 mb with 30% uncertainty.

Note also discrepancies in resonance integrals (in barns) between evaluated libraries and ATLAS [Mughabghab2006] for both Cr-50(n,g) and Cr-53(n,g)

ReactionENDF/B-VII.1BROND-3.1ATLAS 2006
Cr-50(n,g)7.217.2111.7 +/- 0.2
Cr-53(n,g)8.4211.212.3

Finally, the re-evaluation for ENDF/B-VIII.0 of the ORNL TOF measurement on enriched Cr-53 target [Guber2011] contradicts the increase suggested in Ref. [Koscheev2017] where preliminary data have been used.

Such contradictions need to be resolved thanks to new measurements and evaluation.

References

  • [Guber2011] K.H. Guber, et al., Journal of the Korean Physical Society 59(2), 1685-1688, 2011
  • [Kadonis10] KADoNiS 1.0 (http://exp-astro.physik.uni-frankfurt.de/kadonis1.0)
  • [Koscheev2017] V. Koscheev, et al., EPJ Conf. 146, 06025, 2017
  • [Mughabghab2006] S.F. Mughabghab, Atlas of Neutron Resonances, 5th Edition, Elsevier, 2006
  • [Trkov2018] A. Trkov, O. Cabellos and R. Capote, Sensitivity of selected benchmarks to Cr-53 and Cr-50 capture, January 2018

Comment from requester:

- Cr-50(n,g) may be measured by activation or TOF. An accurate activation measurement at 5 and 25 keV may help in solving the puzzle of Cr capture.
- Cr-53(n,g) can only be measured by TOF. There is no publication of the final analysis of the ORNL TOF measurement using enriched Cr-53 sample.
- Lead Slowing Down Spectrometer (LSDS) measurements of Cr-50, Cr-53 and Cr-52 enriched samples and of Cr-nat sample could be extremely important to validate and select a proper evaluation of Cr capture cross section below 100 keV. These measurements are strongly encouraged as complementary to TOF and feasible activation measurements.

Review comment:

Entry Status:
Work in progress (as of SG-C review of May 2018)

Main references:
Please report any missing information to hprlinfo@oecd-nea.org

Experiments

Theory/Evaluation

Validation

  • V. Koscheev et al., Use the results of measurements on KBR facility for testing of neutron data of main structural materials for fast reactors, EPJ Conferences 146 (2007) 06025

Additional file attached:Trkov2018.pdf
Additional file attached:



Request ID100 Type of the request Special Purpose Quantity
TargetReaction and processIncident EnergySecondary energy or angleTarget uncertaintyCovariance
 92-U-235 (n,f),(p,f) SIG  100 MeV-500 MeV  5 Y
FieldSubfieldDate Request createdDate Request acceptedOngoing action
 Standard ADS 23-MAR-18 11-APR-18 Y

Requester: Dr Roberto CAPOTE NOY at IAEA, AUT
Email: roberto.capotenoy@iaea.org

Project (context):

Impact:

Improvements in the standard cause all measurements relative to that standard to be improved. See Ref. [1].

Accuracy:

5% of the cross-section

Justification document:

There are discrepancies (see Fig. 24 in section III.E, pp.161-162 of Ref. [1]) between different theoretical calculations, data estimated from the (p,f) reaction, and the only measured data set of U-238(n,f) cross section at those energies [2]. New measurements of absolute cross sections of U-235 or U-238 (n,f) and/or U-235 or U-238 (p,f) reactions in the energy range where pion channels begin to play an important role (100-500 MeV) are needed to solve the discrepancies and to reduce the uncertainties of the Neutron Standards in that energy range.

References

  1. A.D. Carlson, et al., Evaluation of the Neutron Data Standards, Nuclear Data Sheets 148, 143-188 (2018)
  2. Z.W. Miller, A Measurement of the Prompt Fission Neutron Energy Spectrum for 235U(n,f) and the Neutron-induced Fission Cross Section for 238U(n,f), PhD Thesis, University of Kentucky (2015); https://uknowledge.uky.edu/physastron_etds/29/

Comment from requester:

At high-energy the (n,f) cross-section can be inferred with rather low uncertainty from (p,f) cross-section measurements, and thanks to this can be used in the neutron standards evaluation.

Review comment:

Entry Status:
Work in progress (as of SG-C review of May 2018)

Main references:
Please report any missing information to hprlinfo@oecd-nea.org

Experiments

  • U-235 measurement performed at n_TOF in 2018

Theory/Evaluation

  • B. Marcinkevicius, S. Simakov, V. Pronyaev, 209Bi(n,f) and natPb(n,f) cross sections as a new reference and extension of the 235U, 238U and 239Pu(n,f) standards up to 1 GeV, IAEA Report INDC(NDS)-0681
  • A.D. Carlson et al., Evaluation of the Neutron Data Standards, NDS 148 (2018) 143

Additional file attached:
Additional file attached:



Request ID101 Type of the request Special Purpose Quantity
TargetReaction and processIncident EnergySecondary energy or angleTarget uncertaintyCovariance
 92-U-238 (n,f),(p,f) SIG  100 MeV-500 MeV  5 Y
FieldSubfieldDate Request createdDate Request acceptedOngoing action
 Standard ADS 23-MAR-18 11-APR-18 Y

Requester: Dr Roberto CAPOTE NOY at IAEA, AUT
Email: roberto.capotenoy@iaea.org

Project (context):

Impact:

Improvements in the standard cause all measurements relative to that standard to be improved. See Ref. [1].

Accuracy:

5% of the cross-section

Justification document:

There are discrepancies (see Fig. 24 in section III.E, pp.161-162 of Ref. [1]) between different theoretical calculations, data estimated from the (p,f) reaction, and the only measured data set of U-238(n,f) cross section at those energies [2]. New measurements of absolute cross sections of U-235 or U-238 (n,f) and/or U-235 or U-238 (p,f) reactions in the energy range where pion channels begin to play an important role (100-500 MeV) are needed to solve the discrepancies and to reduce the uncertainties of the Neutron Standards in that energy range.

References

  1. A.D. Carlson, et al., Evaluation of the Neutron Data Standards, Nuclear Data Sheets 148, 143-188 (2018)
  2. Z.W. Miller, A Measurement of the Prompt Fission Neutron Energy Spectrum for 235U(n,f) and the Neutron-induced Fission Cross Section for 238U(n,f), PhD Thesis, University of Kentucky (2015); https://uknowledge.uky.edu/physastron_etds/29/

Comment from requester:

At high-energy the (n,f) cross-section can be inferred with rather low uncertainty from (p,f) cross-section measurements, and thanks to this can be used in the neutron standards evaluation.

Review comment:

Entry Status:
Work in progress (as of SG-C review of May 2018)

Main references:
Please report any missing information to hprlinfo@oecd-nea.org

Theory/Evaluation

  • B. Marcinkevicius, S. Simakov, V. Pronyaev, 209Bi(n,f) and natPb(n,f) cross sections as a new reference and extension of the 235U, 238U and 239Pu(n,f) standards up to 1 GeV, IAEA Report INDC(NDS)-0681
  • A.D. Carlson et al., Evaluation of the Neutron Data Standards, NDS 148 (2018) 143

Additional file attached:
Additional file attached:



Request ID102 Type of the request High Priority request
TargetReaction and processIncident EnergySecondary energy or angleTarget uncertaintyCovariance
 64-GD-155 (n,g),(n,tot) SIG  Thermal-100 eV  4 Y
FieldSubfieldDate Request createdDate Request acceptedOngoing action
 Fission LWR 07-FEB-18 09-MAY-18 Y

Requester: Mr Cristian MASSIMI at UBOLOGNA, ITY
Email: cristian.massimi@unibo.it

Project (context):

Impact:
In nuclear industry gadolinium is used as neutron absorber having the highest thermal absorption cross section among all stable elements thanks to Gd-155 and especially Gd-157 isotopes. It is commonly used, in PWR or BWR, as burnable absorber in fresh fuel to compensate an excess of reactivity or as emergency shutdown poison in CANDU reactors. RPI measurements of the Gd-157 thermal capture cross-section [1] differ by 10% from the ENDF/B-VI.8 value and, thus, in ENDF/B-VII.1 [2] the low energy cross section uncertainty was increased by up to a factor 2, i.e. from about 2-4% to 4-6%. There is no significant change in the latest ENDF/B-VIII.0 evaluation of these two isotopes. A sensitivity and uncertainty analysis was performed by ENEA to quantify the maximum impact of the uncertainty of the gadolinium isotopes cross sections on the criticality of a LWR system [3-5]. It showed that, in systems with a high number of gadolinium fuel pins, neutron capture of odd gadolinium isotopes contribution to keff uncertainty ranks high, just after the major U-235 and U-238 contributions.

Accuracy:
Sensitivity and uncertainty analyses show that keeping the cross section uncertainty below 4% mitigates the impact on keff uncertainty at high-burnup, which is important for a good estimation of the residual reactivity penalty of a fuel assembly at the end of life.

Justification document:
Despite their importance, the capture cross sections of the odd Gd isotopes have not been extensively studied and are not known with the accuracy required by present-day nuclear industry. In the thermal energy range these cross sections contribute more than 99% to the total cross section. Complementary accurate transmission measurements are also required to constrain the capture cross section. Table 1 in Ref. [4] illustrates current discrepancies for 157Gd capture cross-section at thermal energy. Such contradictions should be clarified thanks to new measurements and evaluation.

References

  1. G. Leinweber, et al., Nuclear Science and Engineering 154, 261-279 (2006)
  2. M. B. Chadwick et al., ENDF/B-VII.1 Nuclear Data for Science and Technology: Cross Sections, Covariances, Fission Product Yields and Decay Data, Nuclear Data Sheets 112, 2887-2996 (2011)
  3. F. Rocchi, 157Gd and 155Gd (n,g) cross section project, JEF/DOC-1835 (2017)
  4. F. Rocchi, A. Guglielmelli, D.M. Castelluccio and C. Massimi, Reassessment of gadolinium odd isotopes neutron cross sections: scientific motivations and sensitivity-uncertainty analysis on LWR fuel assembly criticality calculations, EPJ Nuclear Sci. Technol. 3, 21 (2017)
  5. F. Rocchi, A. Guglielmelli, S. Lo Meo, Implementation of a Cross Section Evaluation Methodology for Safety Margin Analysis: Application to Gadolinium Odd Isotopes, ENEA Report RdS/PAR2015/078 (2016)

Comment from requester:
Beyond nuclear industry, nuclear astrophysics can benefit from the accurate knowledge of 155- and 157-Gd(n,g) cross section up to a few keV, as the even-Gd isotopes play an important role in the s-process nucleosynthesis. Therefore a consistent analysis of all Gd-nat isotopes from thermal up to a few keV is of high interest for both astrophysics and nuclear data evaluation purpose.

Review comment:

Entry Status:
Pending new evaluation or validation (as of SG-C review of May 2018)

Main references:
Please report any missing information to hprlinfo@oecd-nea.org

Experiments

Theory/Evaluation

  • Ongoing work at ORNL and IRSN

Validation

  • F. Rocchi et al., Reassessment of gadolinium odd isotopes neutron cross sections: scientific motivations and sensitivity-uncertainty analysis on LWR fuel assembly criticality calculations, EPJ N 3 (2017) 21
  • F. Rocchi et al., Sensitivity uncertainty analysis and new neutron capture cross-sections for gadolinium odd-isotopes to support nuclear safety, Annals of Nuclear Energy 132 (2019) 537

Additional file attached:ENEA_RdS_PAR2015_078.pdf
Additional file attached:jefdoc-1835.pdf



Request ID103 Type of the request High Priority request
TargetReaction and processIncident EnergySecondary energy or angleTarget uncertaintyCovariance
 64-GD-157 (n,g),(n,tot) SIG  Thermal-100 eV  4 Y
FieldSubfieldDate Request createdDate Request acceptedOngoing action
 Fission LWR 07-FEB-18 09-MAY-18 Y

Requester: Mr Cristian MASSIMI at UBOLOGNA, ITY
Email: cristian.massimi@unibo.it

Project (context):

Impact:
In nuclear industry gadolinium is used as neutron absorber having the highest thermal absorption cross section among all stable elements thanks to Gd-155 and especially Gd-157 isotopes. It is commonly used, in PWR or BWR, as burnable absorber in fresh fuel to compensate an excess of reactivity or as emergency shutdown poison in CANDU reactors. RPI measurements of the Gd-157 thermal capture cross-section [1] differ by 10% from the ENDF/B-VI.8 value and, thus, in ENDF/B-VII.1 [2] the low energy cross section uncertainty was increased by up to a factor 2, i.e. from about 2-4% to 4-6%. There is no significant change in the latest ENDF/B-VIII.0 evaluation of these two isotopes. A sensitivity and uncertainty analysis was performed by ENEA to quantify the maximum impact of the uncertainty of the gadolinium isotopes cross sections on the criticality of a LWR system [3-5]. It showed that, in systems with a high number of gadolinium fuel pins, neutron capture of odd gadolinium isotopes contribution to keff uncertainty ranks high, just after the major U-235 and U-238 contributions.

Accuracy:
Sensitivity and uncertainty analyses show that keeping the cross section uncertainty below 4% mitigates the impact on keff uncertainty at high-burnup, which is important for a good estimation of the residual reactivity penalty of a fuel assembly at the end of life.

Justification document:
Despite their importance, the capture cross sections of the odd Gd isotopes have not been extensively studied and are not known with the accuracy required by present-day nuclear industry. In the thermal energy range these cross sections contribute more than 99% to the total cross section. Complementary accurate transmission measurements are also required to constrain the capture cross section. Table 1 in Ref. [4] illustrates current discrepancies for 157Gd capture cross-section at thermal energy. Such contradictions should be clarified thanks to new measurements and evaluation.

References

  1. G. Leinweber, et al., Nuclear Science and Engineering 154, 261-279 (2006)
  2. M. B. Chadwick et al., ENDF/B-VII.1 Nuclear Data for Science and Technology: Cross Sections, Covariances, Fission Product Yields and Decay Data, Nuclear Data Sheets 112, 2887-2996 (2011)
  3. F. Rocchi, 157Gd and 155Gd (n,g) cross section project, JEF/DOC-1835 (2017)
  4. F. Rocchi, A. Guglielmelli, D.M. Castelluccio and C. Massimi, Reassessment of gadolinium odd isotopes neutron cross sections: scientific motivations and sensitivity-uncertainty analysis on LWR fuel assembly criticality calculations, EPJ Nuclear Sci. Technol. 3, 21 (2017)
  5. F. Rocchi, A. Guglielmelli, S. Lo Meo, Implementation of a Cross Section Evaluation Methodology for Safety Margin Analysis: Application to Gadolinium Odd Isotopes, ENEA Report RdS/PAR2015/078 (2016)

Comment from requester:
Beyond nuclear industry, nuclear astrophysics can benefit from the accurate knowledge of 155- and 157-Gd(n,g) cross section up to a few keV, as the even-Gd isotopes play an important role in the s-process nucleosynthesis. Therefore a consistent analysis of all Gd-nat isotopes from thermal up to a few keV is of high interest for both astrophysics and nuclear data evaluation purpose.

Review comment:

Entry Status:
Pending new evaluation or validation (as of SG-C review of May 2018)

Main references:
Please report any missing information to hprlinfo@oecd-nea.org

Experiments

Theory/Evaluation

  • Ongoing work at ORNL and IRSN

Validation

  • F. Rocchi et al., Reassessment of gadolinium odd isotopes neutron cross sections: scientific motivations and sensitivity-uncertainty analysis on LWR fuel assembly criticality calculations, EPJ N 3 (2017) 21
  • F. Rocchi et al., Sensitivity uncertainty analysis and new neutron capture cross-sections for gadolinium odd-isotopes to support nuclear safety, Annals of Nuclear Energy 132 (2019) 537

Additional file attached:ENEA_RdS_PAR2015_078.pdf
Additional file attached:jefdoc-1835.pdf



Request ID115 Type of the request High Priority request
TargetReaction and processIncident EnergySecondary energy or angleTarget uncertaintyCovariance
 94-PU-239 (n,tot) SIG  Thermal-5 eV  1 Y
FieldSubfieldDate Request createdDate Request acceptedOngoing action
 Fission Thermal reactors 22-MAR-19 08-APR-19 Y

Requester: Dr Gilles NOGUERE at CAD-DER, FR
Email: gilles.noguere@cea.fr

Project (context):

Impact:

The use of new high-accuracy transmission data in the evaluation procedure will affect the partial cross sections and their uncertainties, whose impact on neutronic calculations may be significant. For the first resonance the uncertainty on capture is 2.5% in JEFF-3.3 and 4% in ENDF/B-VIII.0, whereas the sensitivity of keff to capture is close to 200 pcm/% for MOX fuel. Hence, any modifications of the resonance parameters and their uncertainties will have a sizeable impact on reactor applications.

Accuracy:

Accuracy and precision better than 1% are required for the first resonance.

Justification document:

New experimental setups are developed to measure the capture cross sections of actinides in the resolved resonance range. However, total cross sections are also important quantities for evaluation purposes.

The transmission data of the first resonance have all been measured in the 1950's (see attached figure).

Uncertainty information on these old measurements are scarce or lacking and does not help much to constrain the resonance parameters in the evaluation process, which is a pity given the high accuracy that can be reached on a transmission measurement (compared to capture). The attached figure illustrates how ENDF/B-VIII.0 and JEFF-3.3 differs, partly because of evaluators' choices, but also because of poor uncertainty information.

New high-accuracy transmission measurements of the first resonance will help improve the resonance parameters and reduce the uncertainty on the capture cross section.

Comment from requester:

Review comment:

Entry Status:
Work in progress (as of SG-C review of June 2019)

Main references:
Please report any missing information to hprlinfo@oecd-nea.org

  • C. de Saint Jean (coordinator), Co-ordinated Evaluation of Plutonium-239 in the Resonance Region, Nuclear Energy Agency, International Evaluation Cooperation, NEA/WPEC-34, Report NEA/NSC/WPEC/DOC(2014)447 (2014)

Additional file attached:HPRL_Request_Pu239_ntot_1stRes.png
Additional file attached: