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 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 ID7 Type of the request General request
TargetReaction and processIncident EnergySecondary energy or angleTarget uncertaintyCovariance
 26-FE-56 (n,xn) SIG,DDX  7 MeV-20 MeV 1MeV-20MeV 30 
FieldSubfieldDate Request createdDate Request acceptedOngoing action
 Fission,ADS Shielding, Medical, SNS 13-JUL-06 16-APR-07 

Requester: Prof. Arjan KONING at NRGPETTEN, NED
Email:

Project (context): JEFF, Model calculations

Impact:
New double differential experimental data for the Fe(n,xn) reaction will allow a crucial test of the pre-equilibrium models underlying neutron transport libraries for spallation neutron sources. They will thereby enhance the confidence in neutron transport calculations for spallation neutron sources such as envisioned for accelerator driven systems.

Accuracy:
30% for the double-differential spectra

Justification document:
A global pre-equilibrium analysis from 7 to 200 MeV based on the optical model potential, A.J. Koning and M.C. Duijvestijn, Nucl. Phys. A744, 15 (2004).

Comment from requester:
There are hundreds of (p,xp) and (p,xn) spectra in the 20-200 MeV range available, several (n,xp) spectra, but there are basically no double-differential (n,xn) spectra available. The presence of such data would heavily constrain the pre-equilibrium model parameters and thereby result in a much better prediction of neutron-induced spectra in the entire 50-200 MeV range. Since high-energy spectra are rather structureless the choice of target is less essential.

Review comment:

Entry Status:
Completed (as of SG-C review of May 2018) - The experimental program performed at Uppsala [Sagrado:2011] combined with improvements in nuclear reaction models allow modern evaluations to address this request, see e.g. [Herman:2018].

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

Experiments

  • I.C. Sagrado Garcia et al., Neutron production in neutron-induced reactions at 96 MeV on 56Fe and 208Pb, PRC 84 (2011) 044619

Theory/Evaluation

  • M. Herman et al., Evaluation of Neutron Reactions on Iron Isotopes for CIELO and ENDF/B-VIII.0, NDS 148 (2018) 214

Additional file attached:
Additional file attached:



Request ID9 Type of the request General request
TargetReaction and processIncident EnergySecondary energy or angleTarget uncertaintyCovariance
 92-U-233 (n,g) nubar,SIG  Thermal-10 keV  .5 Y
FieldSubfieldDate Request createdDate Request acceptedOngoing action
 Fission Molten Salt Reactors 19-APR-07 19-APR-07 Y

Requester: Dr Adrien BIDAUD at LPSC, FR
Email: bidaud@lpsc.in2p3.fr

Project (context): JEFF

Impact:
U-233 is the main isotope of relevance to the Th/U fuel cycle. The present request concerns the viability of Th/U fueled molten salt reactors which requires that the amount of U-233 generated equals that which is destroyed.

Accuracy:
0.5% in nubar, 5% for the (n,g) cross section

Justification document:
Uncertainties on the predicted regeneration gain inferred from the uncertainties of the nuclear data have been estimated showing a 4200 pcm uncertainty for a regeneration gain designed to be 200 pcm, i.e. very close to a complete balancing of production and destruction of U-233. The main culprits are nubar contributing 2200 pcm and the capture cross section contributing 3260 pcm. A target accuracy of 2000 pcm is required to facilitate defining the reprocessing scheme for a molten salt reactor.
Reference:
A. Bidaud, Impact of Nuclear Data Uncertainties on a GEN IV Thorium Reactor at Equilibrium (attached document).
CEA Technical Note NT-SPRC/LEPH-05/204, G. Noguere et al (attachment 2).

Comment from requester:
Owing to the difficulty in measuring the U-233(n,g) cross section, a new evaluation could be done on the basis of the Profil results (see CEA Technical Note NT-SPRC/LEPH-05/204).

Review comment:

Any effort done to reduce the uncertainties on neutron yields and capture cross section down to less than 1% and about 5% respectively or at least to confirm their uncertainty would be very much appreciated. If the uncertainty on RG could be reduced down to 2000pcm, the needed reprocessing scheme could be designed with more confidence, and then the research on specific goals such as minor actinide and protactinium extraction could be prioritized.

Nubar is currently known to 1%, the capture cross section to 10%. The above mentioned target uncertainties implies that the desired accuracies for improved data are approximately half these numbers.

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

  • J.E. Escher and F.S. Dietrich, Cross sections for neutron capture from surrogate measurements: An examination of Weisskopf-Ewing and ratio approximations, PRC 81 (2010) 024612
  • C. Carrapico, E. Berthoumieux, et al., 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:U233_MSR_Impact.pdf
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 ID11 Type of the request General request
TargetReaction and processIncident EnergySecondary energy or angleTarget uncertaintyCovariance
 94-PU-239 (n,f),(n,g) SIG,eta,alpha  1 meV-1 eV  1 Y
FieldSubfieldDate Request createdDate Request acceptedOngoing action
 Fission Thermal reactors 09-MAY-07 06-JUN-07 Y

Requester: Dr Luiz Carlos LEAL at IRSN, FR
Email: luiz.leal@irsn.fr

Project (context): Thermal reactors

Impact:
Improve the estimation of keff as well as the moderator temperature coefficient for thermal systems. In particular, this concerns MOX cores and Pu solutions.

References:
[1] A. Santamarina, Improvement of the Pu239 Evaluation for JEFF3, JEF/DOC-1158 (attached below)
[2] Russell D. Mosteller, "ENDF/B-VII, ENDF/B-VI, and JENDL-3.3 Results for Unreflected Plutonium Solutions and MOX Lattices", Joint International Topical Meeting on Mathematics & Computation and Supercomputing in Nuclear Applications (M&C + SNA 2007) Monterey, California, April 15-19, 2007, on CD-ROM, American Nuclear Society, LaGrange Park, IL (2007), Los Alamos report: LA-UR-06-6903
[3] D. Bernard, E. Fort, A. Courcelle, A. Santamarina, G. Noguère, "239Pu nuclear data improvements in thermal and epithermal neutron ranges, International Conference on Nuclear Data for Science and Technology 2007, Contrib #708.
[4] H.Weigmann, B.Keck, J.A.Wartena,P.Geltenbort, K.Schreckenbach, Int.Conf.on the Physics of Reactors: Operation, Design and Computation, Marseille, 23-27 Apr 1990.

Accuracy:
< 1 % for fission cross section and < 2 % for capture cross section

Justification document:
Recent benchmark calculations indicate that the shape of sig(n,g), sig(n,f), eta and/or alpha at low energy need to be revised. A similar problem was seen about 10 years ago with the U-235 cross section. In that case the shape of eta at low energy was found to be slightly varying with energy. It appears that a similar problem exists for Pu-239. Existing experimental data have not helped much to solve the puzzle. Measurements of these quantities in the range from 1 meV to 1 eV, including the 0.3 eV resonance, will be of utmost importance.

Comment from requester:
Existing measurements of the Pu-239 fission and capture cross sections (alpha) do not help to resolve a longstanding problem with thermal benchmarks regarding Pu-239. The measurements of Ref. [4] helped resolve a similar problem that previously existed for U-235.

Review comment:
Since the request refers to the resonance region, measurements would be needed to address this request. Quite different measurement samples and detectors would be required for the (n,f) and (n,g) cross section measurements with individual uncertainties that would be easily in excess of 1%. Therefore, to achieve the accuracy, measurements should aim at measuring either eta or alpha in function of energy striving for minimal systematic errors. Such an eta or alpha measurement would need to be combined with a precise fission cross section from an evaluation or an independent measurement. Calibrating a fission deposit mass to 1%, is possible, but poses a challenge. Interested experimental groups should consult Ref. [4].

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

  • 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

Additional file attached:
Additional file attached:jefdoc-1158.pdf



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 ID16 Type of the request General request
TargetReaction and processIncident EnergySecondary energy or angleTarget uncertaintyCovariance
 95-AM-243 (n,f) prompt n  Eth-10 MeV  10 
FieldSubfieldDate Request createdDate Request acceptedOngoing action
 ADS Fast fission spectra 08-NOV-07 10-SEP-08 Y

Requester: Mr Toshinobu SASA at JAEA, JPN
Email: toshinobu.sasa@cao.go.jp

Project (context): J-PARC

Impact:
It is necessary in the ADS design study. Obninsk scientists report important difference of fission neutron spectra from ENDF/B-VI evaluation at MeV energies.

Accuracy:

Justification document:
T. Sugawara, K. Sugino, T. Sasa, "SND2006-V.10: Design of MA-loaded Core Experiments using J-PARC", T. Fukahori (Ed.), Proc. of 2006 Symposium on Nuclear Data, Jan. 25-26, 2007, RICOTTI, Tokai-mura, Ibaraki-ken, Japan, ISBN978-4-89047-138-6, Nuclear Data Division, Atomic Energy Society of Japan (2007) [CD-ROM].

Comment from requester:

Review comment:

It appears that experimental work for the neutron-induced reaction will be near to impossible on account of the required amount of sample material. Could this work be carried out by using a transfer reaction?

The importance of the fission neutron spectrum is not contested. It is a significant problem also for the major actinides and for those it is a recurrent subject of debate. The present request is dubbed a general request since it is not backed by a direct sensitivity study. The methodology of such sensitivity studies was recently explored by WPEC Subgroup 26 (link to WPEC Subgroup 26 Report in PDF format, 6 Mb). In that report it is also mentioned that substantial uncertainties may result from the fission spectrum but that further work is required.

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

  • L.V.Drapchinsky, Measurements of the prompt neutron spectra of minor actinides - Fast neutron induced fission of 241Am and 243Am, thermal neutron induced fission of 243Cm, Report ISTC-1828-01 (2004), EXFOR 41589

Additional file attached:sugawara_t(MA-cores_JPARC).pdf
Additional file attached:



Request ID17 Type of the request General request
TargetReaction and processIncident EnergySecondary energy or angleTarget uncertaintyCovariance
 96-CM-244 (n,f) prompt n  Eth-10 MeV  10 
FieldSubfieldDate Request createdDate Request acceptedOngoing action
 ADS Fast fission spectra 08-NOV-07 10-SEP-08 Y

Requester: Mr Toshinobu SASA at JAEA, JPN
Email: toshinobu.sasa@cao.go.jp

Project (context): J-PARC

Impact:
It is necessary in the ADS design study. Obninsk scientists report important difference of fission neutron spectra from ENDF/B-VI evaluation at MeV energies.

Accuracy:

Justification document:
T. Sugawara, K. Sugino, T. Sasa, "SND2006-V.10: Design of MA-loaded Core Experiments using J-PARC", T. Fukahori (Ed.), Proc. of 2006 Symposium on Nuclear Data, Jan. 25-26, 2007, RICOTTI, Tokai-mura, Ibaraki-ken, Japan, ISBN978-4-89047-138-6, Nuclear Data Division, Atomic Energy Society of Japan (2007) [CD-ROM].

Comment from requester:

Review comment:

It appears that experimental work for the neutron-induced reaction will be near to impossible on account of the required amount of sample material. Could this work be carried out by using a transfer reaction?

The importance of the fission neutron spectrum is not contested. It is a significant problem also for the major actinides and for those it is a recurrent subject of debate. The present request is dubbed a general request since it is not backed by a direct sensitivity study. The methodology of such sensitivity studies was recently explored by WPEC Subgroup 26 (link to WPEC Subgroup 26 Report in PDF format, 6 Mb). In that report it is also mentioned that substantial uncertainties may result from the fission spectrum but that further work is required.

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:sugawara_t(MA-cores_JPARC).pdf
Additional file attached:



ctor 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:
    Non-threshold reactions measured in fast spectra such as the 252Cf(sf) and 235U(nth,f) spectrum tend to have their spectrum averaged cross section dominated by scattering contributions and ‘room-return’ neutrons. Experiments should be designed to minimize these contributions and maximize the reaction rate from the primary source. For new experiments best estimates must be provided by detailed Monte Carlo calculation of the spectrum realized in the experiment and the Monte Carlo model must be made available to IRDFF to facilitate validation of new proposals for the cross section. In all cases it is advised to publish both the fully corrected SACS and the measured reaction rates of the primary reaction and the monitor reactions used for normalization and validation of the model. The measured reaction rates must be provided with a full covariance matrix.

    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:SPA_CE_U235.pdf



    Request ID57 Type of the request Special Purpose Quantity
    TargetReaction and processIncident EnergySecondary energy or angleTarget uncertaintyCovariance
     57-LA-139 (n,g) SIG,SPA  235U(n,f)  2-5 Y
    FieldSubfieldDate Request createdDate Request acceptedOngoing action
     Dosimetry Fast fission, D-T fusion 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:
    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:
    New measurements of the spectrum-averaged cross section are requested to solve C/E discrepancy. See SPA_CE_U235.pdf below.

    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:
    Non-threshold reactions measured in fast spectra such as the 252Cf(sf) and 235U(nth,f) spectrum tend to have their spectrum averaged cross section dominated by scattering contributions and ‘room-return’ neutrons. Experiments should be designed to minimize these contributions and maximize the reaction rate from the primary source. For new experiments best estimates must be provided by detailed Monte Carlo calculation of the spectrum realized in the experiment and the Monte Carlo model must be made available to IRDFF to facilitate validation of new proposals for the cross section. In all cases it is advised to publish both the fully corrected SACS and the measured reaction rates of the primary reaction and the monitor reactions used for normalization and validation of the model. The measured reaction rates must be provided with a full covariance matrix.

    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:SPA_CE_U235.pdf



    Request ID58 Type of the request Special Purpose Quantity
    TargetReaction and processIncident EnergySecondary energy or angleTarget uncertaintyCovariance
     45-RH-103 (n,inl)Rh-103m SIG,SPA  235U(n,f)  2-5 Y
    FieldSubfieldDate Request createdDate Request acceptedOngoing action
     Dosimetry Fast fission, D-T fusion 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:
    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:
    New measurements of the spectrum-averaged cross section are requested to solve C/E discrepancy. See SPA_CE_U235.pdf below.

    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:SPA_CE_U235.pdf



    Request ID59 Type of the request Special Purpose Quantity
    TargetReaction and processIncident EnergySecondary energy or angleTarget uncertaintyCovariance
     69-TM-169 (n,2n) SIG,SPA  235U(n,f)  2-5 Y
    FieldSubfieldDate Request createdDate Request acceptedOngoing action
     Dosimetry D-T fusion 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:
    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].
    Following a recommendation from the IAEA Data Development Project on Neutron Standards [Pronyaev2013], the IRDFF project supports SACS measurements of high-threshold (above 10 MeV) dosimetry cross-sections in well-characterized 252Cf(sf) and 235U(nth,f) neutron fields in order to improve the cross sections and/or the high-energy part of the prompt fission neutron spectra.

    Comment from requester:
    New measurements of the spectrum-averaged cross section are requested to solve C/E discrepancy and for improvement of the cross section and prompt fission neutron spectrum above 10 MeV. See CE_U235_and_HighThreshold.pdf below.

    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.
    • [Pronyaev2013] V.G. Pronyaev, A.D. Carlson and R. Capote Noy, “Toward a New Evaluation of Neutron Standards”, IAEA Technical Meeting, 8-12 July 2013, INDC(NDS)-0641.

    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:CE_U235_and_HighThreshold.pdf



    Request ID60 Type of the request Special Purpose Quantity
    TargetReaction and processIncident EnergySecondary energy or angleTarget uncertaintyCovariance
     29-CU-65 (n,2n) SIG,SPA  235U(n,f)  2-5 Y
    FieldSubfieldDate Request createdDate Request acceptedOngoing action
     Dosimetry D-T fusion 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:
    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].
    Following a recommendation from the IAEA Data Development Project on Neutron Standards [Pronyaev2013], the IRDFF project supports SACS measurements of high-threshold (above 10 MeV) dosimetry cross-sections in well-characterized 252Cf(sf) and 235U(nth,f) neutron fields in order to improve the cross sections and/or the high-energy part of the prompt fission neutron spectra.

    Comment from requester:
    Measurements of the spectrum-averaged cross section are missing for validation purposes and for improvement of the cross section and prompt fission neutron spectrum above 10 MeV. See Cf252U235_HighThreshold.pdf below.

    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.
    • [Pronyaev2013] V.G. Pronyaev, A.D. Carlson and R. Capote Noy, “Toward a New Evaluation of Neutron Standards”, IAEA Technical Meeting, 8-12 July 2013, INDC(NDS)-0641.

    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:Cf252U235_HighThreshold.pdf



    Request ID61 Type of the request Special Purpose Quantity
    TargetReaction and processIncident EnergySecondary energy or angleTarget uncertaintyCovariance
     25-MN-55 (n,2n) SIG,SPA  235U(n,f)  2-5 Y
    FieldSubfieldDate Request createdDate Request acceptedOngoing action
     Dosimetry D-T fusion 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:
    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].
    Following a recommendation from the IAEA Data Development Project on Neutron Standards [Pronyaev2013], the IRDFF project supports SACS measurements of high-threshold (above 10 MeV) dosimetry cross-sections in well-characterized 252Cf(sf) and 235U(nth,f) neutron fields in order to improve the cross sections and/or the high-energy part of the prompt fission neutron spectra.

    Comment from requester:
    New measurements of the spectrum-averaged cross section are requested to solve C/E discrepancy and for improvement of the cross section and prompt fission neutron spectrum above 10 MeV. See SPA_CE_U235.pdf below.

    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.
    • [Pronyaev2013] V.G. Pronyaev, A.D. Carlson and R. Capote Noy, “Toward a New Evaluation of Neutron Standards”, IAEA Technical Meeting, 8-12 July 2013, INDC(NDS)-0641.

    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:SPA_CE_U235.pdf



    Request ID62 Type of the request Special Purpose Quantity
    TargetReaction and processIncident EnergySecondary energy or angleTarget uncertaintyCovariance
     28-NI-58 (n,2n) SIG,SPA  235U(n,f)  2-5 Y
    FieldSubfieldDate Request createdDate Request acceptedOngoing action
     Dosimetry D-T fusion 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:
    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].
    Following a recommendation from the IAEA Data Development Project on Neutron Standards [Pronyaev2013], the IRDFF project supports SACS measurements of high-threshold (above 10 MeV) dosimetry cross-sections in well-characterized 252Cf(sf) and 235U(nth,f) neutron fields in order to improve the cross sections and/or the high-energy part of the prompt fission neutron spectra.

    Comment from requester:
    New measurements of the spectrum-averaged cross section are requested to solve C/E discrepancy and for improvement of the cross section and prompt fission neutron spectrum above 10 MeV. See SPA_CE_U235.pdf below.

    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.
    • [Pronyaev2013] V.G. Pronyaev, A.D. Carlson and R. Capote Noy, “Toward a New Evaluation of Neutron Standards”, IAEA Technical Meeting, 8-12 July 2013, INDC(NDS)-0641.

    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:SPA_CE_U235.pdf



    Request ID63 Type of the request Special Purpose Quantity
    TargetReaction and processIncident EnergySecondary energy or angleTarget uncertaintyCovariance
     95-AM-241 (n,f) SIG,SPA  252Cf(sf)-235U(n,f)  2-5 Y
    FieldSubfieldDate Request createdDate Request acceptedOngoing action
     Dosimetry Fast fission, D-T fusion 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:
    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:
    Measurements of the spectrum-averaged cross section are missing for validation purposes.

    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:
    Non-threshold reactions measured in fast spectra such as the 252Cf(sf) and 235U(nth,f) spectrum tend to have their spectrum averaged cross section dominated by scattering contributions and ‘room-return’ neutrons. Experiments should be designed to minimize these contributions and maximize the reaction rate from the primary source. For new experiments best estimates must be provided by detailed Monte Carlo calculation of the spectrum realized in the experiment and the Monte Carlo model must be made available to IRDFF to facilitate validation of new proposals for the cross section. In all cases it is advised to publish both the fully corrected SACS and the measured reaction rates of the primary reaction and the monitor reactions used for normalization and validation of the model. The measured reaction rates must be provided with a full covariance matrix.

    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 ID64 Type of the request Special Purpose Quantity
    TargetReaction and processIncident EnergySecondary energy or angleTarget uncertaintyCovariance
     15-P-31 (n,p) SIG,SPA  252Cf(sf)-235U(n,f)  2-5 Y
    FieldSubfieldDate Request createdDate Request acceptedOngoing action
     Dosimetry Fast fission, D-T fusion 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:
    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:
    Measurements of the 252Cf(sf)-spectrum-averaged cross section are missing for validation purposes. New measurements of the 235U(n,f)-spectrum-averaged cross section are requested to solve C/E discrepancy. See SPA_CE_Cf252U235.pdf below.

    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:SPA_CE_Cf252U235.pdf



    Request ID65 Type of the request Special Purpose Quantity
    TargetReaction and processIncident EnergySecondary energy or angleTarget uncertaintyCovariance
     92-U-238 (n,2n) SIG,SPA  252Cf(sf)-235U(n,f)  2-5 Y
    FieldSubfieldDate Request createdDate Request acceptedOngoing action
     Dosimetry Fast fission, D-T fusion 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:
    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:
    New measurements of the spectrum-averaged cross section are requested to solve C/E discrepancy and for improvement of the prompt fission neutron spectrum at high energy. See CE_Cf252U235_and_HighThreshold.pdf below.

    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:CE_Cf252U235_and_HighThreshold.pdf



    Request ID66 Type of the request Special Purpose Quantity
    TargetReaction and processIncident EnergySecondary energy or angleTarget uncertaintyCovariance
     49-IN-115 (n,2n)In-114m SIG,SPA  252Cf(sf)-235U(n,f)  2-5 Y
    FieldSubfieldDate Request createdDate Request acceptedOngoing action
     Dosimetry D-T fusion 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:
    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].
    Following a recommendation from the IAEA Data Development Project on Neutron Standards [Pronyaev2013], the IRDFF project supports SACS measurements of high-threshold (above 10 MeV) dosimetry cross-sections in well-characterized 252Cf(sf) and 235U(nth,f) neutron fields in order to improve the cross sections and/or the high-energy part of the prompt fission neutron spectra.

    Comment from requester:
    Measurements of the spectrum-averaged cross section are missing for validation purposes and for improvement of the cross section and prompt fission neutron spectrum above 10 MeV. See Cf252U235_HighThreshold.pdf below.

    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.
    • [Pronyaev2013] V.G. Pronyaev, A.D. Carlson and R. Capote Noy, “Toward a New Evaluation of Neutron Standards”, IAEA Technical Meeting, 8-12 July 2013, INDC(NDS)-0641.

    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:Cf252U235_HighThreshold.pdf



    Request ID67 Type of the request Special Purpose Quantity
    TargetReaction and processIncident EnergySecondary energy or angleTarget uncertaintyCovariance
     59-PR-141 (n,2n) SIG,SPA  252Cf(sf)-235U(n,f)  2-5 Y
    FieldSubfieldDate Request createdDate Request acceptedOngoing action
     Dosimetry D-T fusion 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:
    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].
    Following a recommendation from the IAEA Data Development Project on Neutron Standards [Pronyaev2013], the IRDFF project supports SACS measurements of high-threshold (above 10 MeV) dosimetry cross-sections in well-characterized 252Cf(sf) and 235U(nth,f) neutron fields in order to improve the cross sections and/or the high-energy part of the prompt fission neutron spectra.

    Comment from requester:
    Measurements of the spectrum-averaged cross section are missing for validation purposes and for improvement of the cross section and prompt fission neutron spectrum above 10 MeV. See Cf252U235_HighThreshold.pdf below.

    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.
    • [Pronyaev2013] V.G. Pronyaev, A.D. Carlson and R. Capote Noy, “Toward a New Evaluation of Neutron Standards”, IAEA Technical Meeting, 8-12 July 2013, INDC(NDS)-0641.

    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:Cf252U235_HighThreshold.pdf



    Request ID68 Type of the request Special Purpose Quantity
    TargetReaction and processIncident EnergySecondary energy or angleTarget uncertaintyCovariance
     24-CR-52 (n,2n) SIG,SPA  252Cf(sf)-235U(n,f)  2-5 Y
    FieldSubfieldDate Request createdDate Request acceptedOngoing action
     Dosimetry D-T fusion 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:
    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].
    Following a recommendation from the IAEA Data Development Project on Neutron Standards [Pronyaev2013], the IRDFF project supports SACS measurements of high-threshold (above 10 MeV) dosimetry cross-sections in well-characterized 252Cf(sf) and 235U(nth,f) neutron fields in order to improve the cross sections and/or the high-energy part of the prompt fission neutron spectra.

    Comment from requester:
    Measurements of the spectrum-averaged cross section are missing for validation purposes and for improvement of the cross section and prompt fission neutron spectrum above 10 MeV. See Cf252U235_HighThreshold.pdf below.

    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.
    • [Pronyaev2013] V.G. Pronyaev, A.D. Carlson and R. Capote Noy, “Toward a New Evaluation of Neutron Standards”, IAEA Technical Meeting, 8-12 July 2013, INDC(NDS)-0641.

    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:Cf252U235_HighThreshold.pdf



    Request ID69 Type of the request Special Purpose Quantity
    TargetReaction and processIncident EnergySecondary energy or angleTarget uncertaintyCovariance
     11-NA-23 (n,2n) SIG,SPA  252Cf(sf)-235U(n,f)  2-5 Y
    FieldSubfieldDate Request createdDate Request acceptedOngoing action
     Dosimetry D-T fusion 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:
    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].
    Following a recommendation from the IAEA Data Development Project on Neutron Standards [Pronyaev2013], the IRDFF project supports SACS measurements of high-threshold (above 10 MeV) dosimetry cross-sections in well-characterized 252Cf(sf) and 235U(nth,f) neutron fields in order to improve the cross sections and/or the high-energy part of the prompt fission neutron spectra.

    Comment from requester:
    Measurements of the spectrum-averaged cross section are missing for validation purposes and for improvement of the cross section and prompt fission neutron spectrum above 10 MeV. See Cf252U235_HighThreshold.pdf below.

    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.
    • [Pronyaev2013] V.G. Pronyaev, A.D. Carlson and R. Capote Noy, “Toward a New Evaluation of Neutron Standards”, IAEA Technical Meeting, 8-12 July 2013, INDC(NDS)-0641.

    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:Cf252U235_HighThreshold.pdf



    Request ID70 Type of the request Special Purpose Quantity
    TargetReaction and processIncident EnergySecondary energy or angleTarget uncertaintyCovariance
     13-AL-27 (n,2n) SIG,SPA  252Cf(sf)-235U(n,f)  2-5 Y
    FieldSubfieldDate Request createdDate Request acceptedOngoing action
     Dosimetry D-T fusion 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:
    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].
    Following a recommendation from the IAEA Data Development Project on Neutron Standards [Pronyaev2013], the IRDFF project supports SACS measurements of high-threshold (above 10 MeV) dosimetry cross-sections in well-characterized 252Cf(sf) and 235U(nth,f) neutron fields in order to improve the cross sections and/or the high-energy part of the prompt fission neutron spectra.

    Comment from requester:
    Measurements of the spectrum-averaged cross section are missing for validation purposes and for improvement of the cross section and prompt fission neutron spectrum above 10 MeV. See Cf252U235_HighThreshold.pdf below.

    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.
    • [Pronyaev2013] V.G. Pronyaev, A.D. Carlson and R. Capote Noy, “Toward a New Evaluation of Neutron Standards”, IAEA Technical Meeting, 8-12 July 2013, INDC(NDS)-0641.

    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:Cf252U235_HighThreshold.pdf



    Request ID71 Type of the request Special Purpose Quantity
    TargetReaction and processIncident EnergySecondary energy or angleTarget uncertaintyCovariance
     22-TI-46 (n,2n) SIG,SPA  252Cf(sf)-235U(n,f)  2-5 Y
    FieldSubfieldDate Request createdDate Request acceptedOngoing action
     Dosimetry D-T fusion 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:
    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].
    Following a recommendation from the IAEA Data Development Project on Neutron Standards [Pronyaev2013], the IRDFF project supports SACS measurements of high-threshold (above 10 MeV) dosimetry cross-sections in well-characterized 252Cf(sf) and 235U(nth,f) neutron fields in order to improve the cross sections and/or the high-energy part of the prompt fission neutron spectra.

    Comment from requester:
    Measurements of the spectrum-averaged cross section are requested for validation purposes in 235U(n,f) neutron fields, for solving C/E discrepancy in 252Cf(sf) fields, and for improvement of the cross section and prompt fission neutron spectrum above 10 MeV. See CE_Cf252U235_and_HighThreshold.pdf below.

    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.
    • [Pronyaev2013] V.G. Pronyaev, A.D. Carlson and R. Capote Noy, “Toward a New Evaluation of Neutron Standards”, IAEA Technical Meeting, 8-12 July 2013, INDC(NDS)-0641.

    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:CE_Cf252U235_and_HighThreshold.pdf



    Request ID72 Type of the request Special Purpose Quantity
    TargetReaction and processIncident EnergySecondary energy or angleTarget uncertaintyCovariance
     50-SN-117 (n,inl)Sn-117m SIG,SPA  252Cf(sf)-235U(n,f)  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

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



    Request ID73 Type of the request Special Purpose Quantity
    TargetReaction and processIncident EnergySecondary energy or angleTarget uncertaintyCovariance
     22-TI-47 (n,np) SIG,SPA  252Cf(sf)-235U(n,f)  5-10 Y
    FieldSubfieldDate Request createdDate Request acceptedOngoing action
     Dosimetry D-T fusion, 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].
    Following a recommendation from the IAEA Data Development Project on Neutron Standards [Pronyaev2013], the IRDFF project supports SACS measurements of high-threshold (above 10 MeV) dosimetry cross-sections in well-characterized 252Cf(sf) and 235U(nth,f) neutron fields in order to improve the cross sections and/or the high-energy part of the prompt fission neutron spectra.

    Comment from requester:
    Measurements of the spectrum-averaged cross section are missing for validation purposes and for improvement of the cross section and prompt fission neutron spectrum above 10 MeV.

    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.
    • [Pronyaev2013] V.G. Pronyaev, A.D. Carlson and R. Capote Noy, “Toward a New Evaluation of Neutron Standards”, IAEA Technical Meeting, 8-12 July 2013, INDC(NDS)-0641.

    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 ID74 Type of the request Special Purpose Quantity
    TargetReaction and processIncident EnergySecondary energy or angleTarget uncertaintyCovariance
     22-TI-48 (n,np) SIG,SPA  252Cf(sf)-235U(n,f)  5-10 Y
    FieldSubfieldDate Request createdDate Request acceptedOngoing action
     Dosimetry D-T fusion, 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].
    Following a recommendation from the IAEA Data Development Project on Neutron Standards [Pronyaev2013], the IRDFF project supports SACS measurements of high-threshold (above 10 MeV) dosimetry cross-sections in well-characterized 252Cf(sf) and 235U(nth,f) neutron fields in order to improve the cross sections and/or the high-energy part of the prompt fission neutron spectra.

    Comment from requester:
    Measurements of the spectrum-averaged cross section are missing for validation purposes and for improvement of the cross section and prompt fission neutron spectrum above 10 MeV.

    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.
    • [Pronyaev2013] V.G. Pronyaev, A.D. Carlson and R. Capote Noy, “Toward a New Evaluation of Neutron Standards”, IAEA Technical Meeting, 8-12 July 2013, INDC(NDS)-0641.

    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 ID75 Type of the request Special Purpose Quantity
    TargetReaction and processIncident EnergySecondary energy or angleTarget uncertaintyCovariance
     22-TI-49 (n,np) SIG,SPA  252Cf(sf)-235U(n,f)  5-10 Y
    FieldSubfieldDate Request createdDate Request acceptedOngoing action
     Dosimetry D-T fusion, 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].
    Following a recommendation from the IAEA Data Development Project on Neutron Standards [Pronyaev2013], the IRDFF project supports SACS measurements of high-threshold (above 10 MeV) dosimetry cross-sections in well-characterized 252Cf(sf) and 235U(nth,f) neutron fields in order to improve the cross sections and/or the high-energy part of the prompt fission neutron spectra.

    Comment from requester:
    Measurements of the spectrum-averaged cross section are missing for validation purposes and for improvement of the cross section and prompt fission neutron spectrum above 10 MeV.

    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.
    • [Pronyaev2013] V.G. Pronyaev, A.D. Carlson and R. Capote Noy, “Toward a New Evaluation of Neutron Standards”, IAEA Technical Meeting, 8-12 July 2013, INDC(NDS)-0641.

    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 ID76 Type of the request Special Purpose Quantity
    TargetReaction and processIncident EnergySecondary energy or angleTarget uncertaintyCovariance
     26-FE-54 (n,2n) SIG,SPA  252Cf(sf)-235U(n,f)  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].
    Following a recommendation from the IAEA Data Development Project on Neutron Standards [Pronyaev2013], the IRDFF project supports SACS measurements of high-threshold (above 10 MeV) dosimetry cross-sections in well-characterized 252Cf(sf) and 235U(nth,f) neutron fields in order to improve the cross sections and/or the high-energy part of the prompt fission neutron spectra.

    Comment from requester:
    Measurements of the spectrum-averaged cross section are missing for validation purposes and for improvement of the cross section and prompt fission neutron spectrum above 10 MeV. See Cf252U235_HighThreshold.pdf below.

    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.
    • [Pronyaev2013] V.G. Pronyaev, A.D. Carlson and R. Capote Noy, “Toward a New Evaluation of Neutron Standards”, IAEA Technical Meeting, 8-12 July 2013, INDC(NDS)-0641.

    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:Cf252U235_HighThreshold.pdf



    Request ID77 Type of the request Special Purpose Quantity
    TargetReaction and processIncident EnergySecondary energy or angleTarget uncertaintyCovariance
     69-TM-169 (n,3n) SIG,SPA  252Cf(sf)-235U(n,f)  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].
    Following a recommendation from the IAEA Data Development Project on Neutron Standards [Pronyaev2013], the IRDFF project supports SACS measurements of high-threshold (above 10 MeV) dosimetry cross-sections in well-characterized 252Cf(sf) and 235U(nth,f) neutron fields in order to improve the cross sections and/or the high-energy part of the prompt fission neutron spectra.

    Comment from requester:
    Measurements of the spectrum-averaged cross section are missing for validation purposes and for improvement of the cross section and prompt fission neutron spectrum above 10 MeV. See Cf252U235_HighThreshold.pdf below.

    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.
    • [Pronyaev2013] V.G. Pronyaev, A.D. Carlson and R. Capote Noy, “Toward a New Evaluation of Neutron Standards”, IAEA Technical Meeting, 8-12 July 2013, INDC(NDS)-0641.

    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:Cf252U235_HighThreshold.pdf



    Request ID78 Type of the request Special Purpose Quantity
    TargetReaction and processIncident EnergySecondary energy or angleTarget uncertaintyCovariance
     83-BI-209 (n,3n) SIG,SPA  252Cf(sf)-235U(n,f)  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].
    Following a recommendation from the IAEA Data Development Project on Neutron Standards [Pronyaev2013], the IRDFF project supports SACS measurements of high-threshold (above 10 MeV) dosimetry cross-sections in well-characterized 252Cf(sf) and 235U(nth,f) neutron fields in order to improve the cross sections and/or the high-energy part of the prompt fission neutron spectra.

    Comment from requester:
    Measurements of the spectrum-averaged cross section are missing for validation purposes and for improvement of the cross section and prompt fission neutron spectrum above 10 MeV. See Cf252U235_HighThreshold.pdf below.

    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.
    • [Pronyaev2013] V.G. Pronyaev, A.D. Carlson and R. Capote Noy, “Toward a New Evaluation of Neutron Standards”, IAEA Technical Meeting, 8-12 July 2013, INDC(NDS)-0641.

    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:Cf252U235_HighThreshold.pdf



    Request ID79 Type of the request Special Purpose Quantity
    TargetReaction and processIncident EnergySecondary energy or angleTarget uncertaintyCovariance
     27-CO-59 (n,3n) SIG,SPA  252Cf(sf)-235U(n,f)  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].
    Following a recommendation from the IAEA Data Development Project on Neutron Standards [Pronyaev2013], the IRDFF project supports SACS measurements of high-threshold (above 10 MeV) dosimetry cross-sections in well-characterized 252Cf(sf) and 235U(nth,f) neutron fields in order to improve the cross sections and/or the high-energy part of the prompt fission neutron spectra.

    Comment from requester:
    Measurements of the spectrum-averaged cross section are missing for validation purposes and for improvement of the cross section and prompt fission neutron spectrum above 10 MeV. See Cf252U235_HighThreshold.pdf below.

    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.
    • [Pronyaev2013] V.G. Pronyaev, A.D. Carlson and R. Capote Noy, “Toward a New Evaluation of Neutron Standards”, IAEA Technical Meeting, 8-12 July 2013, INDC(NDS)-0641.

    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:Cf252U235_HighThreshold.pdf



    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 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 ID104 Type of the request Special Purpose Quantity
    TargetReaction and processIncident EnergySecondary energy or angleTarget uncertaintyCovariance
     9-F-19 (n,2n) SIG,SPA  239Pu(n,f)  3 Y
    FieldSubfieldDate Request createdDate Request acceptedOngoing action
     Fission Dosimetry 26-MAR-18 06-JUN-18 

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

    Project (context):

    Impact:
    A better knowledge of the prompt fission neutron spectrum (PFNS) from Pu-239 thermal-neutron induced fission is important for high-burnup fuels and new generation reactors. This is especially true when considering neutron radiation damage from the PFNS high-energy tail, which can be improved thanks to the measurements of spectrum-averaged cross section (SACS) of well-known high-threshold dosimetry reactions.
    Deficiency in Pu-239(n,f) PFNS at large outgoing energies may be responsible for the discrepancies shown in Fig. 178 above 7.5 MeV of average reaction energy, see Fig. 178 in Ref. [1].

    Accuracy:
    3% cross-section ratio uncertainty relative to reference cross sections

    Justification document:
    No SACS measurements exist in Pu-239(nth,f) prompt neutron field. In the latest IAEA evaluation, the extrapolation of Pu-239(nth,f) PFNS to outgoing energies above 8 MeV is based on SACS estimated by interpolation between SACS measured in U-233, U-235 and Cf-252 prompt neutron fields, see page 74-76, Fig. 43 and Table XXVI in Ref. [2].

    References

    1. 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, Nuclear Data Sheets 148 (2018) 1 (http://doi.org/10.1016/j.nds.2018.02.001)
    2. R. Capote et al., Prompt Fission Neutron Spectra of Actinides, Nuclear Data Sheets 131 (2016) 1 (http://doi.org/10.1016/j.nds.2015.12.002)

    Comment from requester:
    SACS measurements of high-threshold dosimetry reactions are requested to improve further the high-energy tail of Pu-239(nth,f) PFNS above 8 MeV of outgoing energy. These measurements should be performed relative to high-threshold reference cross sections: Al-27(n,a), Au-197(n,2n), Ni-58(n,p).

    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

    Additional file attached:
    Additional file attached:



    Request ID105 Type of the request Special Purpose Quantity
    TargetReaction and processIncident EnergySecondary energy or angleTarget uncertaintyCovariance
     25-MN-55 (n,2n) SIG,SPA  239Pu(n,f)  3 Y
    FieldSubfieldDate Request createdDate Request acceptedOngoing action
     Fission Dosimetry 26-MAR-18 06-JUN-18 

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

    Project (context):

    Impact:
    A better knowledge of the prompt fission neutron spectrum (PFNS) from Pu-239 thermal-neutron induced fission is important for high-burnup fuels and new generation reactors. This is especially true when considering neutron radiation damage from the PFNS high-energy tail, which can be improved thanks to the measurements of spectrum-averaged cross section (SACS) of well-known high-threshold dosimetry reactions.
    Deficiency in Pu-239(n,f) PFNS at large outgoing energies may be responsible for the discrepancies shown in Fig. 178 above 7.5 MeV of average reaction energy, see Fig. 178 in Ref. [1].

    Accuracy:
    3% cross-section ratio uncertainty relative to reference cross sections

    Justification document:
    No SACS measurements exist in Pu-239(nth,f) prompt neutron field. In the latest IAEA evaluation, the extrapolation of Pu-239(nth,f) PFNS to outgoing energies above 8 MeV is based on SACS estimated by interpolation between SACS measured in U-233, U-235 and Cf-252 prompt neutron fields, see page 74-76, Fig. 43 and Table XXVI in Ref. [2].

    References

    1. 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, Nuclear Data Sheets 148 (2018) 1 (http://doi.org/10.1016/j.nds.2018.02.001)
    2. R. Capote et al., Prompt Fission Neutron Spectra of Actinides, Nuclear Data Sheets 131 (2016) 1 (http://doi.org/10.1016/j.nds.2015.12.002)

    Comment from requester:
    SACS measurements of high-threshold dosimetry reactions are requested to improve further the high-energy tail of Pu-239(nth,f) PFNS above 8 MeV of outgoing energy. These measurements should be performed relative to high-threshold reference cross sections: Al-27(n,a), Au-197(n,2n), Ni-58(n,p).

    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

    Additional file attached:
    Additional file attached:



    Request ID106 Type of the request Special Purpose Quantity
    TargetReaction and processIncident EnergySecondary energy or angleTarget uncertaintyCovariance
     27-CO-59 (n,2n) SIG,SPA  239Pu(n,f)  3 Y
    FieldSubfieldDate Request createdDate Request acceptedOngoing action
     Fission Dosimetry 26-MAR-18 06-JUN-18 

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

    Project (context):

    Impact:
    A better knowledge of the prompt fission neutron spectrum (PFNS) from Pu-239 thermal-neutron induced fission is important for high-burnup fuels and new generation reactors. This is especially true when considering neutron radiation damage from the PFNS high-energy tail, which can be improved thanks to the measurements of spectrum-averaged cross section (SACS) of well-known high-threshold dosimetry reactions.
    Deficiency in Pu-239(n,f) PFNS at large outgoing energies may be responsible for the discrepancies shown in Fig. 178 above 7.5 MeV of average reaction energy, see Fig. 178 in Ref. [1].

    Accuracy:
    3% cross-section ratio uncertainty relative to reference cross sections

    Justification document:
    No SACS measurements exist in Pu-239(nth,f) prompt neutron field. In the latest IAEA evaluation, the extrapolation of Pu-239(nth,f) PFNS to outgoing energies above 8 MeV is based on SACS estimated by interpolation between SACS measured in U-233, U-235 and Cf-252 prompt neutron fields, see page 74-76, Fig. 43 and Table XXVI in Ref. [2].

    References

    1. 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, Nuclear Data Sheets 148 (2018) 1 (http://doi.org/10.1016/j.nds.2018.02.001)
    2. R. Capote et al., Prompt Fission Neutron Spectra of Actinides, Nuclear Data Sheets 131 (2016) 1 (http://doi.org/10.1016/j.nds.2015.12.002)

    Comment from requester:
    SACS measurements of high-threshold dosimetry reactions are requested to improve further the high-energy tail of Pu-239(nth,f) PFNS above 8 MeV of outgoing energy. These measurements should be performed relative to high-threshold reference cross sections: Al-27(n,a), Au-197(n,2n), Ni-58(n,p).

    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

    Additional file attached:
    Additional file attached:



    Request ID107 Type of the request Special Purpose Quantity
    TargetReaction and processIncident EnergySecondary energy or angleTarget uncertaintyCovariance
     28-NI-58 (n,2n) SIG,SPA  239Pu(n,f)  3 Y
    FieldSubfieldDate Request createdDate Request acceptedOngoing action
     Fission Dosimetry 26-MAR-18 06-JUN-18 

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

    Project (context):

    Impact:
    A better knowledge of the prompt fission neutron spectrum (PFNS) from Pu-239 thermal-neutron induced fission is important for high-burnup fuels and new generation reactors. This is especially true when considering neutron radiation damage from the PFNS high-energy tail, which can be improved thanks to the measurements of spectrum-averaged cross section (SACS) of well-known high-threshold dosimetry reactions.
    Deficiency in Pu-239(n,f) PFNS at large outgoing energies may be responsible for the discrepancies shown in Fig. 178 above 7.5 MeV of average reaction energy, see Fig. 178 in Ref. [1].

    Accuracy:
    3% cross-section ratio uncertainty relative to reference cross sections

    Justification document:
    No SACS measurements exist in Pu-239(nth,f) prompt neutron field. In the latest IAEA evaluation, the extrapolation of Pu-239(nth,f) PFNS to outgoing energies above 8 MeV is based on SACS estimated by interpolation between SACS measured in U-233, U-235 and Cf-252 prompt neutron fields, see page 74-76, Fig. 43 and Table XXVI in Ref. [2].

    References

    1. 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, Nuclear Data Sheets 148 (2018) 1 (http://doi.org/10.1016/j.nds.2018.02.001)
    2. R. Capote et al., Prompt Fission Neutron Spectra of Actinides, Nuclear Data Sheets 131 (2016) 1 (http://doi.org/10.1016/j.nds.2015.12.002)

    Comment from requester:
    SACS measurements of high-threshold dosimetry reactions are requested to improve further the high-energy tail of Pu-239(nth,f) PFNS above 8 MeV of outgoing energy. These measurements should be performed relative to high-threshold reference cross sections: Al-27(n,a), Au-197(n,2n), Ni-58(n,p).

    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

    Additional file attached:
    Additional file attached:



    Request ID108 Type of the request Special Purpose Quantity
    TargetReaction and processIncident EnergySecondary energy or angleTarget uncertaintyCovariance
     33-AS-75 (n,2n) SIG,SPA  239Pu(n,f)  3 Y
    FieldSubfieldDate Request createdDate Request acceptedOngoing action
     Fission Dosimetry 26-MAR-18 06-JUN-18 

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

    Project (context):

    Impact:
    A better knowledge of the prompt fission neutron spectrum (PFNS) from Pu-239 thermal-neutron induced fission is important for high-burnup fuels and new generation reactors. This is especially true when considering neutron radiation damage from the PFNS high-energy tail, which can be improved thanks to the measurements of spectrum-averaged cross section (SACS) of well-known high-threshold dosimetry reactions.
    Deficiency in Pu-239(n,f) PFNS at large outgoing energies may be responsible for the discrepancies shown in Fig. 178 above 7.5 MeV of average reaction energy, see Fig. 178 in Ref. [1].

    Accuracy:
    3% cross-section ratio uncertainty relative to reference cross sections

    Justification document:
    No SACS measurements exist in Pu-239(nth,f) prompt neutron field. In the latest IAEA evaluation, the extrapolation of Pu-239(nth,f) PFNS to outgoing energies above 8 MeV is based on SACS estimated by interpolation between SACS measured in U-233, U-235 and Cf-252 prompt neutron fields, see page 74-76, Fig. 43 and Table XXVI in Ref. [2].

    References

    1. 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, Nuclear Data Sheets 148 (2018) 1 (http://doi.org/10.1016/j.nds.2018.02.001)
    2. R. Capote et al., Prompt Fission Neutron Spectra of Actinides, Nuclear Data Sheets 131 (2016) 1 (http://doi.org/10.1016/j.nds.2015.12.002)

    Comment from requester:
    SACS measurements of high-threshold dosimetry reactions are requested to improve further the high-energy tail of Pu-239(nth,f) PFNS above 8 MeV of outgoing energy. These measurements should be performed relative to high-threshold reference cross sections: Al-27(n,a), Au-197(n,2n), Ni-58(n,p).

    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

    Additional file attached:
    Additional file attached:



    Request ID109 Type of the request Special Purpose Quantity
    TargetReaction and processIncident EnergySecondary energy or angleTarget uncertaintyCovariance
     39-Y-89 (n,2n) SIG,SPA  239Pu(n,f)  3 Y
    FieldSubfieldDate Request createdDate Request acceptedOngoing action
     Fission Dosimetry 26-MAR-18 06-JUN-18 

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

    Project (context):

    Impact:
    A better knowledge of the prompt fission neutron spectrum (PFNS) from Pu-239 thermal-neutron induced fission is important for high-burnup fuels and new generation reactors. This is especially true when considering neutron radiation damage from the PFNS high-energy tail, which can be improved thanks to the measurements of spectrum-averaged cross section (SACS) of well-known high-threshold dosimetry reactions.
    Deficiency in Pu-239(n,f) PFNS at large outgoing energies may be responsible for the discrepancies shown in Fig. 178 above 7.5 MeV of average reaction energy, see Fig. 178 in Ref. [1].

    Accuracy:
    3% cross-section ratio uncertainty relative to reference cross sections

    Justification document:
    No SACS measurements exist in Pu-239(nth,f) prompt neutron field. In the latest IAEA evaluation, the extrapolation of Pu-239(nth,f) PFNS to outgoing energies above 8 MeV is based on SACS estimated by interpolation between SACS measured in U-233, U-235 and Cf-252 prompt neutron fields, see page 74-76, Fig. 43 and Table XXVI in Ref. [2].

    References

    1. 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, Nuclear Data Sheets 148 (2018) 1 (http://doi.org/10.1016/j.nds.2018.02.001)
    2. R. Capote et al., Prompt Fission Neutron Spectra of Actinides, Nuclear Data Sheets 131 (2016) 1 (http://doi.org/10.1016/j.nds.2015.12.002)

    Comment from requester:
    SACS measurements of high-threshold dosimetry reactions are requested to improve further the high-energy tail of Pu-239(nth,f) PFNS above 8 MeV of outgoing energy. These measurements should be performed relative to high-threshold reference cross sections: Al-27(n,a), Au-197(n,2n), Ni-58(n,p).

    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

    Additional file attached:
    Additional file attached:



    Request ID110 Type of the request Special Purpose Quantity
    TargetReaction and processIncident EnergySecondary energy or angleTarget uncertaintyCovariance
     40-ZR-90 (n,2n) SIG,SPA  239Pu(n,f)  3 Y
    FieldSubfieldDate Request createdDate Request acceptedOngoing action
     Fission Dosimetry 26-MAR-18 06-JUN-18 

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

    Project (context):

    Impact:
    A better knowledge of the prompt fission neutron spectrum (PFNS) from Pu-239 thermal-neutron induced fission is important for high-burnup fuels and new generation reactors. This is especially true when considering neutron radiation damage from the PFNS high-energy tail, which can be improved thanks to the measurements of spectrum-averaged cross section (SACS) of well-known high-threshold dosimetry reactions.
    Deficiency in Pu-239(n,f) PFNS at large outgoing energies may be responsible for the discrepancies shown in Fig. 178 above 7.5 MeV of average reaction energy, see Fig. 178 in Ref. [1].

    Accuracy:
    3% cross-section ratio uncertainty relative to reference cross sections

    Justification document:
    No SACS measurements exist in Pu-239(nth,f) prompt neutron field. In the latest IAEA evaluation, the extrapolation of Pu-239(nth,f) PFNS to outgoing energies above 8 MeV is based on SACS estimated by interpolation between SACS measured in U-233, U-235 and Cf-252 prompt neutron fields, see page 74-76, Fig. 43 and Table XXVI in Ref. [2].

    References

    1. 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, Nuclear Data Sheets 148 (2018) 1 (http://doi.org/10.1016/j.nds.2018.02.001)
    2. R. Capote et al., Prompt Fission Neutron Spectra of Actinides, Nuclear Data Sheets 131 (2016) 1 (http://doi.org/10.1016/j.nds.2015.12.002)

    Comment from requester:
    SACS measurements of high-threshold dosimetry reactions are requested to improve further the high-energy tail of Pu-239(nth,f) PFNS above 8 MeV of outgoing energy. These measurements should be performed relative to high-threshold reference cross sections: Al-27(n,a), Au-197(n,2n), Ni-58(n,p).

    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

    Additional file attached:
    Additional file attached:



    Request ID111 Type of the request Special Purpose Quantity
    TargetReaction and processIncident EnergySecondary energy or angleTarget uncertaintyCovariance
     41-NB-93 (n,2n)Nb-92m SIG,SPA  239Pu(n,f)  3 Y
    FieldSubfieldDate Request createdDate Request acceptedOngoing action
     Fission Dosimetry 26-MAR-18 06-JUN-18 

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

    Project (context):

    Impact:
    A better knowledge of the prompt fission neutron spectrum (PFNS) from Pu-239 thermal-neutron induced fission is important for high-burnup fuels and new generation reactors. This is especially true when considering neutron radiation damage from the PFNS high-energy tail, which can be improved thanks to the measurements of spectrum-averaged cross section (SACS) of well-known high-threshold dosimetry reactions.
    Deficiency in Pu-239(n,f) PFNS at large outgoing energies may be responsible for the discrepancies shown in Fig. 178 above 7.5 MeV of average reaction energy, see Fig. 178 in Ref. [1].

    Accuracy:
    3% cross-section ratio uncertainty relative to reference cross sections

    Justification document:
    No SACS measurements exist in Pu-239(nth,f) prompt neutron field. In the latest IAEA evaluation, the extrapolation of Pu-239(nth,f) PFNS to outgoing energies above 8 MeV is based on SACS estimated by interpolation between SACS measured in U-233, U-235 and Cf-252 prompt neutron fields, see page 74-76, Fig. 43 and Table XXVI in Ref. [2].

    References

    1. 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, Nuclear Data Sheets 148 (2018) 1 (http://doi.org/10.1016/j.nds.2018.02.001)
    2. R. Capote et al., Prompt Fission Neutron Spectra of Actinides, Nuclear Data Sheets 131 (2016) 1 (http://doi.org/10.1016/j.nds.2015.12.002)

    Comment from requester:
    SACS measurements of high-threshold dosimetry reactions are requested to improve further the high-energy tail of Pu-239(nth,f) PFNS above 8 MeV of outgoing energy. These measurements should be performed relative to high-threshold reference cross sections: Al-27(n,a), Au-197(n,2n), Ni-58(n,p).

    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

    Additional file attached:
    Additional file attached:



    Request ID112 Type of the request Special Purpose Quantity
    TargetReaction and processIncident EnergySecondary energy or angleTarget uncertaintyCovariance
     53-I-127 (n,2n) SIG,SPA  239Pu(n,f)  3 Y
    FieldSubfieldDate Request createdDate Request acceptedOngoing action
     Fission Dosimetry 26-MAR-18 06-JUN-18 

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

    Project (context):

    Impact:
    A better knowledge of the prompt fission neutron spectrum (PFNS) from Pu-239 thermal-neutron induced fission is important for high-burnup fuels and new generation reactors. This is especially true when considering neutron radiation damage from the PFNS high-energy tail, which can be improved thanks to the measurements of spectrum-averaged cross section (SACS) of well-known high-threshold dosimetry reactions.
    Deficiency in Pu-239(n,f) PFNS at large outgoing energies may be responsible for the discrepancies shown in Fig. 178 above 7.5 MeV of average reaction energy, see Fig. 178 in Ref. [1].

    Accuracy:
    3% cross-section ratio uncertainty relative to reference cross sections

    Justification document:
    No SACS measurements exist in Pu-239(nth,f) prompt neutron field. In the latest IAEA evaluation, the extrapolation of Pu-239(nth,f) PFNS to outgoing energies above 8 MeV is based on SACS estimated by interpolation between SACS measured in U-233, U-235 and Cf-252 prompt neutron fields, see page 74-76, Fig. 43 and Table XXVI in Ref. [2].

    References

    1. 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, Nuclear Data Sheets 148 (2018) 1 (http://doi.org/10.1016/j.nds.2018.02.001)
    2. R. Capote et al., Prompt Fission Neutron Spectra of Actinides, Nuclear Data Sheets 131 (2016) 1 (http://doi.org/10.1016/j.nds.2015.12.002)

    Comment from requester:
    SACS measurements of high-threshold dosimetry reactions are requested to improve further the high-energy tail of Pu-239(nth,f) PFNS above 8 MeV of outgoing energy. These measurements should be performed relative to high-threshold reference cross sections: Al-27(n,a), Au-197(n,2n), Ni-58(n,p).

    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

    Additional file attached:
    Additional file attached:



    Request ID113 Type of the request Special Purpose Quantity
    TargetReaction and processIncident EnergySecondary energy or angleTarget uncertaintyCovariance
     69-TM-169 (n,2n) SIG,SPA  239Pu(n,f)  3 Y
    FieldSubfieldDate Request createdDate Request acceptedOngoing action
     Fission Dosimetry 26-MAR-18 06-JUN-18 

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

    Project (context):

    Impact:
    A better knowledge of the prompt fission neutron spectrum (PFNS) from Pu-239 thermal-neutron induced fission is important for high-burnup fuels and new generation reactors. This is especially true when considering neutron radiation damage from the PFNS high-energy tail, which can be improved thanks to the measurements of spectrum-averaged cross section (SACS) of well-known high-threshold dosimetry reactions.
    Deficiency in Pu-239(n,f) PFNS at large outgoing energies may be responsible for the discrepancies shown in Fig. 178 above 7.5 MeV of average reaction energy, see Fig. 178 in Ref. [1].

    Accuracy:
    3% cross-section ratio uncertainty relative to reference cross sections

    Justification document:
    No SACS measurements exist in Pu-239(nth,f) prompt neutron field. In the latest IAEA evaluation, the extrapolation of Pu-239(nth,f) PFNS to outgoing energies above 8 MeV is based on SACS estimated by interpolation between SACS measured in U-233, U-235 and Cf-252 prompt neutron fields, see page 74-76, Fig. 43 and Table XXVI in Ref. [2].

    References

    1. 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, Nuclear Data Sheets 148 (2018) 1 (http://doi.org/10.1016/j.nds.2018.02.001)
    2. R. Capote et al., Prompt Fission Neutron Spectra of Actinides, Nuclear Data Sheets 131 (2016) 1 (http://doi.org/10.1016/j.nds.2015.12.002)

    Comment from requester:
    SACS measurements of high-threshold dosimetry reactions are requested to improve further the high-energy tail of Pu-239(nth,f) PFNS above 8 MeV of outgoing energy. These measurements should be performed relative to high-threshold reference cross sections: Al-27(n,a), Au-197(n,2n), Ni-58(n,p).

    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

    Additional file attached:
    Additional file attached: