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

Theory/Evaluation

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

Validation

• M. Salvatores, et al., Methods and Issues for the Combined Use of Integral Experiments and Covariance Data: Results of a NEA International Collaborative Study, Nuclear Data Sheets 118 (2014) 38
• G. Palmiotti, et al., Combined Use of Integral Experiments and Covariance Data, Nuclear Data Sheets 118 (2014) 596

Justification document:

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

Comment from requester:

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

Review comment:

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

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

Experiments

Additional file attached:Trkov2018.pdf
Additional file attached:

Request ID	15		Type of the request	High Priority request
Target	Reaction and process	Incident Energy	Secondary energy or angle	Target uncertainty	Covariance
95-AM-241	(n,g),(n,tot) SIG	Thermal-Fast		See details
Field	Subfield	Date Request created	Date Request accepted	Ongoing action
Fission	LWR, Thermal	08-NOV-07	10-SEP-08	Y

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

Project (context): JENDL and WPEC subgroup 26

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

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

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

Energy Range	Uncertainty (%)
	Initial	GFR	ADMAB
67.4 -183 keV	7	4	2
24.8 -67.4 keV	8	3	2
9.12 -24.8 keV	7	3	2
2.03 -9.12 keV	7	3	2
0.454-2.03 keV	7	3	3

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

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

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

Entry Status:
Work in progress (as of SG-C review of May 2018)
Completed at thermal energies (as of SG-C review of May 2022) - SG41 has reviewed all available data, addressed discrepancies and produced recommendations for Am-241 nuclear data. These data have been incorporated into new evaluations.
Work in progress at fast energies (as of SG-C review of May 2022)

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

Experiments

• S. Nakamura et al., Thermal-Neutron Capture Cross Section and Resonance Integral of Americium-241, JNST 44 (2007) 1500, EXFOR 22998
• M. Jandel et al., Neutron capture cross section of 241Am, PRC 78 (2008) 034609, EXFOR 14209
• C. Lampoudis et al., Neutron transmission and capture cross section measurements for 241Am at the GELINA facility, Eur. Phys. J. Plus (2013) 128:86, EXFOR 23139
• K. Fraval et al., Measurement and analysis of the 241Am(n,g) cross section with liquid scintillator detectors using time-of-flight spectroscopy at the n_TOF facility at CERN, PRC 89 (2014) 044609, EXFOR 23237
• H. Harada et al., Capture Cross-section Measurement of 241Am(n,g) at J-PARC/MLF/ANNRI, NDS 119 (2014) 61, EXFOR 23172
• K. Terada et al., Measurements of gamma-ray emission probabilities of 241,243Am and 239Np, JNST 53 (2016) 1881
• K. Hirose et al., Simultaneous measurement of neutron-induced fission and capture cross sections for 241Am at neutron energies below fission threshold, NIM A 856 (2017) 133, EXFOR 23338
• K. Terada et al., Measurements of neutron total and capture cross sections of 241Am with ANNRI at J-PARC, Journal of Nuclear Science and Technology 55 (2018) 1198
• E. Mendoza et al., Measurement and analysis of the 241Am neutron capture cross section at the n_TOF facility at CERN, PRC 97 (2018) 054616
• New capture measurement performed in 2017 at n_TOF EAR2

Theory/Evaluation

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

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

Request ID	14		Type of the request	General request
Target	Reaction and process	Incident Energy	Secondary energy or angle	Target uncertainty	Covariance
94-PU-242	(n,g),(n,tot) SIG	0.5 eV-2.0 keV		8	Y
Field	Subfield	Date Request created	Date Request accepted	Ongoing 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

• G. Palmiotti, et al., Combined Use of Integral Experiments and Covariance Data, Nuclear Data Sheets 118 (2014) 596

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

Request ID	102		Type of the request	High Priority request
Target	Reaction and process	Incident Energy	Secondary energy or angle	Target uncertainty	Covariance
64-GD-155	(n,g),(n,tot) SIG	Thermal-100 eV		4	Y
Field	Subfield	Date Request created	Date Request accepted	Ongoing action
Fission	LWR	07-FEB-18	09-MAY-18	Y

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

Project (context):

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

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

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

References

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

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

Review comment:

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

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

Experiments

• G. Leinweber et al., Neutron capture and total cross-section measurements and resonance parameters of gadolinium, Nuclear Science and Engineering 154 (2006) 261
• B. Baramsai et al., Neutron resonance parameters in 155Gd measured with the DANCE g-ray calorimeter array, Phys. Rev. C 85 (2012) 024622
• H.D. Choi et al., Radiative capture cross sections of 155,157Gd for thermal neutrons, Nucl. Science and Eng. 177 (2014) 219
• Y.-R. Kang et al., Neutron capture measurements and resonance parameters of gadolinium, Nucl. Science and Eng. 180 (2015) 86
• M. Mastromarco, et al., Cross section measurements of 155,157Gd(n,g) induced by thermal and epithermal neutrons, Eur. Phys. J. A 55 (2019) 9
• Yong-uk Kye, et al., Resonance parameters of Gd isotopes derived from capture measurements at GELINA, Eur. Phys. J. A 56 (2020) 30
• R. Mucciola, et al., Results of time-of-flight transmission measurements for 155,157Gd at a 10m station of GELINA, IAEA INDC Report, INDC(EUR)-0037 (2020)
• A. Kimura, et al., Neutron capture and total cross-section measurements of 155Gd and 157Gd at ANNRI in J-PARC, EPJ Conf. 239 (2020) 01012

Theory/Evaluation

• L. Leal, et al., Resonance evaluation of Gadolinium isotopes, EPJ Conf. 239 (2020) 11004

Validation

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

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

Request ID	103		Type of the request	High Priority request
Target	Reaction and process	Incident Energy	Secondary energy or angle	Target uncertainty	Covariance
64-GD-157	(n,g),(n,tot) SIG	Thermal-100 eV		4	Y
Field	Subfield	Date Request created	Date Request accepted	Ongoing action
Fission	LWR	07-FEB-18	09-MAY-18	Y

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

Project (context):

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

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

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

References

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

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

Review comment:

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

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

Experiments

• G. Leinweber et al., Neutron capture and total cross-section measurements and resonance parameters of gadolinium, Nuclear Science and Engineering 154 (2006) 261
• H.D. Choi et al., Radiative capture cross sections of 155,157Gd for thermal neutrons, Nucl. Science and Eng. 177 (2014) 219
• Y.-R. Kang et al., Neutron capture measurements and resonance parameters of gadolinium, Nucl. Science and Eng. 180 (2015) 86
• M. Mastromarco, et al., Cross section measurements of 155,157Gd(n,g) induced by thermal and epithermal neutrons, Eur. Phys. J. A 55 (2019) 9
• Yong-uk Kye, et al., Resonance parameters of Gd isotopes derived from capture measurements at GELINA, Eur. Phys. J. A 56 (2020) 30
• R. Mucciola, et al., Results of time-of-flight transmission measurements for 155,157Gd at a 10m station of GELINA, IAEA INDC Report, INDC(EUR)-0037 (2020)
• A. Kimura, et al., Neutron capture and total cross-section measurements of 155Gd and 157Gd at ANNRI in J-PARC, EPJ Conf. 239 (2020) 01012

Theory/Evaluation

• L. Leal, et al., Resonance evaluation of Gadolinium isotopes, EPJ Conf. 239 (2020) 11004

Validation

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

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

Request ID	29		Type of the request	High Priority request
Target	Reaction and process	Incident Energy	Secondary energy or angle	Target uncertainty	Covariance
11-NA-23	(n,inl) SIG	0.5 MeV-1.3 MeV	Emis spec.	See details	Y
Field	Subfield	Date Request created	Date Request accepted	Ongoing action
Fission	Fast Reactors (SFR)	04-APR-08	12-SEP-08

Requester: Prof. Massimo SALVATORES at CADARACHE, FR
Email:

Project (context): NEA WPEC Subgroup 26

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

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

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

Energy Range	Target versus initial uncertainties (%)
	Initial	ABTR	SFR	EFR
1.35 - 2.23 MeV	13		9
0.498 - 1.35 MeV	28	10	4	8

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

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

Review comment:

Entry Status:
Work in progress (as of SG-C review of May 2018)
Pending new evaluation or validation (as of SG-C review of June 2019)
Completed (as of SG-C review of May 2021) - The Na-23 inelastic scattering cross section has been accurately measured at JRC-Geel [Rouki, 2012]. In the framework of the ASTRID SFR project a new evaluation based on both differential and integral information has been prepared for JEFF-3.2 [Archier, 2011, 2014] and adopted in JEFF-3.3 with uncertainties matching the request.

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

Experiments

• C. Rouki et al., High resolution measurement of neutron inelastic scattering cross-sections for 23Na, NIM A 672 (2012) 82, EXFOR 23137
• J.R. Vanhoy et al., Neutron scattering differential cross-sections for 23Na from 1.5 to 4.5 MeV, Nucl. Phys. A 939 (2015) 121, EXFOR 14403

Theory/Evaluation

• S. Kopecky and A. Plompen, R-matrix analysis of the total and inelastic scattering cross sections, EUR 25067 EN (2011)
• M. Herman et al., COMMARA-2.0 Neutron Cross-Section Covariance Library, Report BNL- 94830-2011, Brookhaven National Laboratory (2011)
• P. Archier et al., 23Na evaluation with CONRAD for fast reactor applications, Journal of Korean Physical Society 59 (2011) 915
• P. Archier et al., New JEFF-3.2 Sodium Neutron Induced Cross-sections Evaluation for Neutron Fast Reactors Applications: from 0 to 20 MeV, NDS 118 (2014) 140
• D. Rochman et al., On the evaluation of 23Na neutron-induced reactions and validations, NIM A 612 (2010) 374
• Evaluation work in the framework of INDEN (CIELO follow-up), see Summary Report of the IAEA CM, 15-17 May 2019, Vienna, Report INDC(NDS)-0788
• P. Tamagno, et al., New 23Na evaluation in the resolved resonance range taking into account both differential and double differential experiments, EPJ Conf. 239 (2020) 11006

Validation

• M. Salvatores, et al., Methods and Issues for the Combined Use of Integral Experiments and Covariance Data: Results of a NEA International Collaborative Study, Nuclear Data Sheets 118 (2014) 38
• G. Palmiotti, et al., Combined Use of Integral Experiments and Covariance Data, Nuclear Data Sheets 118 (2014) 596
• Y.-K. Lee, E. Brun, Investigation of Nuclear Data Libraries with TRIPOLI-4 Monte Carlo Code for Sodium-cooled Fast Reactors, Nuclear Data Sheets 118 (2014) 433

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

Request ID	18		Type of the request	High Priority request
Target	Reaction and process	Incident Energy	Secondary energy or angle	Target uncertainty	Covariance
92-U-238	(n,inl) SIG	65 keV-20 MeV	Emis spec.	See details	Y
Field	Subfield	Date Request created	Date Request accepted	Ongoing action
Fission	Fast Reactors EFR,SFR,ABTR...	28-MAR-08	11-SEP-08	Y

Requester: Prof. Massimo SALVATORES at CADARACHE, FR
Email:

Project (context): NEA WPEC Subgroup 26

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

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

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

Energy Range	Initial versus target uncertainties (%)
	Initial	ABTR	SFR	EFR	GFR	LFR
6.07-19.6 MeV	29	12			7
2.23-6.07 MeV	20	3	5	4	2	3
1.35-2.23 MeV	21	4	5	4	2	2
0.498-1.35 MeV	12	7	6	5	2	2
67.4-183 keV	11	7		9	7	4

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

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

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

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

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

Experiments

• M. Kerveno et al., (n,xn gamma) reaction cross section measurements for (n,xn) reaction studies, EPJ Conferences 42 (2013) 01005, EXFOR 22795
• A.M. Daskalakis et al., Quasi-differential neutron scattering from 238U from 0.5 to 20 MeV, Annals of Nuclear Energy 73 (2014) 455
• M. Kerveno, et al., From gamma emissions to (n,xn) cross sections of interest: the role of GAINS and GRAPhEME in nuclear reaction modelling, Eur. Phys. J. A, 51 12 (2015) 167
• M. Kerveno, et al., Measurement of 238U(n,n'γ) cross section data and their impact on reaction models, Phys. Rev. C 104 (2021) 044605

Theory/Evaluation

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

Validation

• M. Salvatores, et al., Methods and Issues for the Combined Use of Integral Experiments and Covariance Data: Results of a NEA International Collaborative Study, Nuclear Data Sheets 118 (2014) 38
• G. Palmiotti, et al., Combined Use of Integral Experiments and Covariance Data, Nuclear Data Sheets 118 (2014) 596

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

Request ID	42		Type of the request	High Priority request
Target	Reaction and process	Incident Energy	Secondary energy or angle	Target uncertainty	Covariance
82-PB-207	(n,inl) SIG	0.5 MeV-6 MeV		See details	Y
Field	Subfield	Date Request created	Date Request accepted	Ongoing action
Fission	Fast Reactors	15-SEP-08	15-SEP-08	Y

Requester: Prof. Massimo SALVATORES at CADARACHE, FR
Email:

Project (context): CEA Cadarache

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

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

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

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

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

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

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

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

Experiments

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

Theory/Evaluation

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

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

Request ID	41		Type of the request	High Priority request
Target	Reaction and process	Incident Energy	Secondary energy or angle	Target uncertainty	Covariance
82-PB-206	(n,inl) SIG	0.5 MeV-6 MeV		See details	Y
Field	Subfield	Date Request created	Date Request accepted	Ongoing action
Fission	Fast Reactors	15-SEP-08	15-SEP-08	Y

Requester: Prof. Massimo SALVATORES at CADARACHE, FR
Email:

Project (context): CEA Cadarache

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

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

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

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

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

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

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

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

Experiments

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

Theory/Evaluation

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

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

Request ID	40		Type of the request	High Priority request
Target	Reaction and process	Incident Energy	Secondary energy or angle	Target uncertainty	Covariance
14-SI-28	(n,inl) SIG	1.4 MeV-6 MeV		See details	Y
Field	Subfield	Date Request created	Date Request accepted	Ongoing action
Fission	Fast Reactors	15-SEP-08	15-SEP-08

Requester: Prof. Massimo SALVATORES at CADARACHE, FR
Email:

Project (context): CEA Cadarache

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

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

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

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

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

Review comment:

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

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

Experiments

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

Theory/Evaluation

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

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

Request ID	34		Type of the request	High Priority request
Target	Reaction and process	Incident Energy	Secondary energy or angle	Target uncertainty	Covariance
26-FE-56	(n,inl) SIG	0.5 MeV-20 MeV	Emis spec.	See details	Y
Field	Subfield	Date Request created	Date Request accepted	Ongoing action
Fission	ADMAB and SFR	04-APR-08	12-SEP-08	Y

Requester: Prof. Massimo SALVATORES at CADARACHE, FR
Email:

Project (context): NEA WPEC Subgroup 26

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

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

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

Energy Range	Initial versus target uncertainties (%)
	Initial	ABTR			SFR			EFR		LFR		ADMAB
		λ=1	λ≠1,a	λ≠1,b	λ=1	λ≠1,a	λ≠1,b	λ=1	λ≠1,a	λ=1	λ≠1,a	λ=1	λ≠1,a
6.07 - 19.6 MeV	13				9	11	13
2.23 - 6.07 MeV	7				4	5	7					3	3
1.35 - 2.23 MeV	25	6	7	10	3	4	7	7	7	4	6	2	2
0.498 - 1.35 MeV	16	8	9	13	3	4	6	8	9	4	5	2	2

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

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

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

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

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

Experiments

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

Theory/Evaluation

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

Validation

• C. Jouanne, Sensitivity of the Shielding Benchmarks on Variance-covariance Data for Scattering Angular Distributions, Nuclear Data Sheets 118 (2014) 384
• I. Kodeli, A. Trkov, G. Zerovnik, Benchmark analysis of iron neutron cross-sections, Jozef Stefan Institute, Ljubljana, Slovenia, Report IJS-DP-11544 (2014)
• M. Salvatores, et al., Methods and Issues for the Combined Use of Integral Experiments and Covariance Data: Results of a NEA International Collaborative Study, Nuclear Data Sheets 118 (2014) 38
• G. Palmiotti, et al., Combined Use of Integral Experiments and Covariance Data, Nuclear Data Sheets 118 (2014) 596
• A. Shaw, et al., Validation of Continuous-Energy ENDF/B-VIII.0 16O, 56Fe, and 63,65Cu Cross Sections for Nuclear Criticality Safety Applications, Nuclear Science and Engineering 195 (2021) 412

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

Request ID	80		Type of the request	Special Purpose Quantity
Target	Reaction and process	Incident Energy	Secondary energy or angle	Target uncertainty	Covariance
50-SN-117	(n,inl)Sn-117m SIG	5 MeV-10 MeV		2-5	Y
Field	Subfield	Date Request created	Date Request accepted	Ongoing 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

• S. Bourganel, et al., Analysis of the FLUOLE-2 program: UOX/MOX core loading configurations, 16th International Symposium on Reactor Dosimetry, May 7-12, 2017, Santa Fe (NM), USA, ASTM International, 2018, STP1608, pp. 296-307

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

Request ID	1		Type of the request	General request
Target	Reaction and process	Incident Energy	Secondary energy or angle	Target uncertainty	Covariance
14-SI-28	(n,np) SIG	Threshold-20 MeV	4 pi	20	Y
Field	Subfield	Date Request created	Date Request accepted	Ongoing action
Fusion	Material Recycling	21-SEP-05	23-MAR-07

Requester: Dr Edward T. CHENG at GA, 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

• Hong-Yu Zhou et al., NIM A 648 (2011) 192, EXFOR 32688

Theory/Evaluation

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

Additional file attached:
Additional file attached:

Request ID	82		Type of the request	Special Purpose Quantity
Target	Reaction and process	Incident Energy	Secondary energy or angle	Target uncertainty	Covariance
39-Y-89	(n,p) SIG	15 MeV-100 MeV		5-10	Y
Field	Subfield	Date Request created	Date Request accepted	Ongoing action
Dosimetry	High-energy	06-OCT-17	06-OCT-17

Requester: Dr Stanislav SIMAKOV at KIT, GER
Email: intersurfen@gmail.com

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 ID	119		Type of the request	High Priority request
Target	Reaction and process	Incident Energy	Secondary energy or angle	Target uncertainty	Covariance
17-CL-35	(n,p) SIG	100 keV-5 MeV		5-8	Y
Field	Subfield	Date Request created	Date Request accepted	Ongoing action
Fission	Gen-IV	09-MAR-22	17-APR-22	Y

Requester: at ,
Email:

Project (context): Gen-IV (fast chloride molten salt reactor design)

Impact:

Requester: Tom Taylor (Moltex Energy) and Tommy Cisneros (TerraPower)

There is currently large uncertainty in reactivity for chloride fast reactors, due mainly to the uncertainty in the Cl-35 (n,p) cross section at high energies. This is a difficulty for chloride fast reactor design because the required fissile loading has large uncertainty, and this uncertainty also propagates to other parameters important to safety, such as reactivity coefficients. Production of S-35 via this reaction is also important for corrosion.

Additionally, above 1.2 MeV there is no uncertainty available for Cl-35 (n,p) in any evaluated library, except TENDL. This makes it difficult to justify a reasonable total uncertainty.

A number of organisations are designing or studying chloride fast reactors and are therefore sensitive to this nuclear data. In addition to Moltex Energy and TerraPower (MCRE and MCFR) the CEA is performing chloride fast reactor R&D. Previous work led by EDF R&D on the REBUS-3700 fast chloride reactor also concluded that more accurate nuclear data for Cl was needed (Mourogov & Bokov, 2006).

It is also worth noting that other Cl nuclear data is important for chloride fast reactors, particularly Cl-35 (n,gamma) and Cl-36 capture, for Cl-36 waste considerations.

Accuracy:

To achieve a target k-eff uncertainty < 300 pcm, the table below suggests uncertainties < 2% would be required above ~100 keV. However, such a low uncertainty is unlikely to be achievable using differential measurements. k-eff uncertainty > 300 pcm would be tolerable, given the uncertainty is currently estimated to be at least ~1000 pcm. On this basis a target of 5 – 8 % is suggested.

It is realised that it may be challenging to achieve even this uncertainty. Any reduction in uncertainty, and/or improved covariances, would be valuable. Integral experiments would likely be needed to reduce uncertainties to a level of 2 – 3 %.

Justification document:

33 group sensitivity coefficients have been generated for the main output parameters, as part of a collaboration with ANL (using the PERSENT code and ENDF/B-VII.0 data). Those for Cl-35 (n,p) are large, as expected, see attached Figure 1.

Uncertainties and target uncertainties have then been derived by UPM through WPEC SG46, using this sensitivity data. Using the TENDL-2021 evaluation for Cl-35, and ENDF/B-VII.1 otherwise, gives a total uncertainty of 836 pcm, with 631 pcm from Cl-35 alone, and dominated by the (n,p) cross section (595 pcm, next largest 173 pcm from (n,alpha)). Below is a table showing target accuracy requirements for the top 10 most important reactions for the Moltex SSR-W.

Recent measurements in the US (Batchelder et al., 2019) and (Kuvin et al., 2020) also indicate that the cross section in all libraries could be too high above ~1.2 MeV. Direct perturbation of the Cl-35 (n,p) reaction in this energy range shows large sensitivity (increase of ~1000 pcm for reduction by 50% between 2.23 and 3.68 MeV).

TerraPower indicates also that very recent measurements (Warren, 2021) of the 35Cl(n,p) cross section have significantly disagree with the evaluated nuclear data in ENDF/B-VIII.0 that was not updated in the last update of chlorine nuclear data – ENDF/B-VII.1. The attached Figure 2 presents the discrepancy between evaluated data and recent measurements.

Comment from requester:

The tables below are reproduced, with permission, from A Review of the Nuclear Data Adjustment Activities within WPEC Sub-groups, O. Cabellos, WANDA 2022, March 2022.

Target accuracy requirements for total k-eff uncertainty < 300 pcm, with nuclear data from ENDF/B-VII.1 (Cl-35 uncertainty from TENDL-2021).

Rank#	Reaction	Energy group	Current (%)	Target (%)	Rel. unc. reduction (%)
1	Cl35 (n,p)	2	6.6	0.9	37.4
2	Cl35 (n,p)	3	12	1.6	14.9
3	Pu239(n,gamma)	4	8.4	1.3	12
4	Cl35 (n,p)	1	8.4	1.2	8.9
5	Pu239(n,gamma)	3	10.4	2.0	4.6
6	Fe56(n,elastic)	3	9.2	1.9	4.3
7	Fe56(n,gamma)	3	16.8	2.8	1.8
8	Pu240(n,gamma)	2	59.3	4.2	1.8
9	Cl35(n,p)	4	11.1	3.7	1.5
10	Fe56(elastic)	2	5.4	1.9	1.3

Boundaries of energy groups

Group#	Lower energy (eV)	Upper energy (eV)	Description
1	2.23130E+06	1.96403E+07	Above threshold fertile
2	4.97871E+05	2.23130E+06	Above threshold inelastic
3	6.73795E+04	4.97871E+05	Continuum to URR
4	2.03468E+03	6.73795E+04	URR
5	2.26033E+01	2.03468E+03	RRR
6	5.40000E-01	2.26033E+01	Epithermal
7	1.40000E-05	5.40000E-01	Thermal

Review comment:

Entry Status:
Work in progress (as of SG-C review of May 2022)

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

Additional file attached:Fig1_Sensitivity.png
Additional file attached:Fig2_35Cl_np.png

Request ID	45		Type of the request	High Priority request
Target	Reaction and process	Incident Energy	Secondary energy or angle	Target uncertainty	Covariance
19-K-39	(n,p),(n,np) SIG	10 MeV-20 MeV		10	Y
Field	Subfield	Date Request created	Date Request accepted	Ongoing action
Fusion		17-MAY-17	11-JUL-17	Y

Requester: Dr Stanislav SIMAKOV at KIT, GER
Email: intersurfen@gmail.com

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

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

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

Justification document:

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

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

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

References

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

Comment from requester:

Review comment:

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

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

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

Request ID	115		Type of the request	High Priority request
Target	Reaction and process	Incident Energy	Secondary energy or angle	Target uncertainty	Covariance
94-PU-239	(n,tot) SIG	Thermal-5 eV		1	Y
Field	Subfield	Date Request created	Date Request accepted	Ongoing action
Fission	Thermal reactors	22-MAR-19	08-APR-19	Y

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

Project (context):

Impact:

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

Accuracy:

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

Justification document:

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

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

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

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

Comment from requester:

Review comment:

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

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

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

Additional file attached:HPRL_Request_Pu239_ntot_1stRes.png
Additional file attached:

Request ID	10		Type of the request	General request
Target	Reaction and process	Incident Energy	Secondary energy or angle	Target uncertainty	Covariance
79-AU-197	(n,tot) SIG	5 keV-200 keV		5
Field	Subfield	Date Request created	Date Request accepted	Ongoing 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

• G. Zerovnik et al., Use of the Grenoble lead slowing-down experiment for cross section validation, IAEA Consultants Meeting, 8-10 October 2013

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

Request ID	81		Type of the request	Special Purpose Quantity
Target	Reaction and process	Incident Energy	Secondary energy or angle	Target uncertainty	Covariance
26-FE-0	(n,x)Mn-54 SIG	15 MeV-100 MeV		5-10	Y
Field	Subfield	Date Request created	Date Request accepted	Ongoing action
Dosimetry	High-energy	06-OCT-17	06-OCT-17

Requester: Dr Stanislav SIMAKOV at KIT, GER
Email: intersurfen@gmail.com

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, 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

• K.I. Zolotarev, Evaluation of 50Cr(n,g)51Cr, 56Fe(n,x)54Mn, 57Fe(n,x)56Mn, and 68Zn(n,x)67Cu reaction cross sections for the IRDFF library, IAEA Report INDC(NDS)-0796 (2019)
• A. Trkov et al., IRDFF-II: A New Neutron Metrology Library, Nuclear Data Sheets 163 (2020) 1

Additional file attached:Simakov2017.pdf
Additional file attached:

Request ID	84		Type of the request	Special Purpose Quantity
Target	Reaction and process	Incident Energy	Secondary energy or angle	Target uncertainty	Covariance
22-TI-0	(n,x)Sc-46 SIG	15 MeV-100 MeV		5-10	Y
Field	Subfield	Date Request created	Date Request accepted	Ongoing action
Dosimetry	High-energy	06-OCT-17	06-OCT-17

Requester: Dr Stanislav SIMAKOV at KIT, GER
Email: intersurfen@gmail.com

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

• A. Trkov et al., IRDFF-II: A New Neutron Metrology Library, Nuclear Data Sheets 163 (2020) 1

Additional file attached:Simakov2017.pdf
Additional file attached:

Request ID	85		Type of the request	Special Purpose Quantity
Target	Reaction and process	Incident Energy	Secondary energy or angle	Target uncertainty	Covariance
22-TI-0	(n,x)Sc-47 SIG	15 MeV-100 MeV		5-10	Y
Field	Subfield	Date Request created	Date Request accepted	Ongoing action
Dosimetry	High-energy	06-OCT-17	06-OCT-17

Requester: Dr Stanislav SIMAKOV at KIT, GER
Email: intersurfen@gmail.com

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

• A. Trkov et al., IRDFF-II: A New Neutron Metrology Library, Nuclear Data Sheets 163 (2020) 1

Additional file attached:Simakov2017.pdf
Additional file attached:

Request ID	86		Type of the request	Special Purpose Quantity
Target	Reaction and process	Incident Energy	Secondary energy or angle	Target uncertainty	Covariance
22-TI-0	(n,x)Sc-48 SIG	15 MeV-100 MeV		5-10	Y
Field	Subfield	Date Request created	Date Request accepted	Ongoing action
Dosimetry	High-energy	06-OCT-17	06-OCT-17

Requester: Dr Stanislav SIMAKOV at KIT, GER
Email: intersurfen@gmail.com

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

• A. Trkov et al., IRDFF-II: A New Neutron Metrology Library, Nuclear Data Sheets 163 (2020) 1

Additional file attached:Simakov2017.pdf
Additional file attached:

Request ID	13		Type of the request	General request
Target	Reaction and process	Incident Energy	Secondary energy or angle	Target uncertainty	Covariance
24-CR-52	(n,xd),(n,xt) SIG	Threshold-65 MeV		20	Y
Field	Subfield	Date Request created	Date Request accepted	Ongoing 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

• P. Pereslavtsev et al., Evaluation of 50Cr, 52Cr, 53Cr, 54Cr Neutron Cross Section Data for Energies up to 200 MeV, Journal of the Korean Physical Society 59 (2011) 931

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

Request ID	92		Type of the request	Special Purpose Quantity
Target	Reaction and process	Incident Energy	Secondary energy or angle	Target uncertainty	Covariance
69-TM-169	(n,xn) x=2-3 SIG	15 MeV-100 MeV		5-10	Y
Field	Subfield	Date Request created	Date Request accepted	Ongoing action
Dosimetry	High-energy	06-OCT-17	06-OCT-17

Requester: Dr Stanislav SIMAKOV at KIT, GER
Email: intersurfen@gmail.com

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, 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
• M. Schulc, et al., Measurement of very high threshold reactions using 252Cf source, Applied Radiation and Isotopes 166 (2020) 109355

Theory/Evaluation

• A. Trkov et al., IRDFF-II: A New Neutron Metrology Library, Nuclear Data Sheets 163 (2020) 1

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

Request ID	83		Type of the request	Special Purpose Quantity
Target	Reaction and process	Incident Energy	Secondary energy or angle	Target uncertainty	Covariance
39-Y-89	(n,xn) x=2-4 SIG	15MeV/Thr.-100 MeV		5-10	Y
Field	Subfield	Date Request created	Date Request accepted	Ongoing action
Dosimetry	High-energy	06-OCT-17	06-OCT-17

Requester: Dr Stanislav SIMAKOV at KIT, GER
Email: intersurfen@gmail.com

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

• P. Chudoba, et al., Activation Measurements of Cross Sections for Ground and Isomeric States Production in Neutron Threshold Reactions on Y and Au, Nuclear Science and Engineering 191 (2018) 150-160

Theory/Evaluation

• A. Trkov et al., IRDFF-II: A New Neutron Metrology Library, Nuclear Data Sheets 163 (2020) 1

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

Request ID	87		Type of the request	Special Purpose Quantity
Target	Reaction and process	Incident Energy	Secondary energy or angle	Target uncertainty	Covariance
71-LU-175	(n,xn) x=2-4 SIG	15MeV/Thr.-100 MeV		5-10	Y
Field	Subfield	Date Request created	Date Request accepted	Ongoing action
Dosimetry	High-energy	06-OCT-17	06-OCT-17

Requester: Dr Stanislav SIMAKOV at KIT, GER
Email: intersurfen@gmail.com

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 ID	88		Type of the request	Special Purpose Quantity
Target	Reaction and process	Incident Energy	Secondary energy or angle	Target uncertainty	Covariance
41-NB-93	(n,xn) x=2-4 SIG	15MeV/Thr.-100 MeV		5-10	Y
Field	Subfield	Date Request created	Date Request accepted	Ongoing action
Dosimetry	High-energy	06-OCT-17	06-OCT-17

Requester: Dr Stanislav SIMAKOV at KIT, GER
Email: intersurfen@gmail.com

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

• A. Trkov et al., IRDFF-II: A New Neutron Metrology Library, Nuclear Data Sheets 163 (2020) 1

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

Request ID	93		Type of the request	Special Purpose Quantity
Target	Reaction and process	Incident Energy	Secondary energy or angle	Target uncertainty	Covariance
83-BI-209	(n,xn) x=3-10 SIG	20MeV/Thr.-150 MeV		5-10	Y
Field	Subfield	Date Request created	Date Request accepted	Ongoing action
Dosimetry	High-energy	06-OCT-17	06-OCT-17

Requester: Dr Stanislav SIMAKOV at KIT, GER
Email: intersurfen@gmail.com

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
• M. Schulc, et al., Constraining high energy tail of ²³⁵U(n_th,f) prompt fission neutron spectrum, Applied Radiation and Isotopes 166 (2020) 109313
• M. Schulc, et al., Measurement of very high threshold reactions using 252Cf source, Applied Radiation and Isotopes 166 (2020) 109355

Theory/Evaluation

• A. Trkov et al., IRDFF-II: A New Neutron Metrology Library, Nuclear Data Sheets 163 (2020) 1

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

Request ID	91		Type of the request	Special Purpose Quantity
Target	Reaction and process	Incident Energy	Secondary energy or angle	Target uncertainty	Covariance
79-AU-197	(n,xn) x=3-5 SIG	20MeV/Thr.-100 MeV		5-10	Y
Field	Subfield	Date Request created	Date Request accepted	Ongoing action
Dosimetry	High-energy	06-OCT-17	06-OCT-17

Requester: Dr Stanislav SIMAKOV at KIT, GER
Email: intersurfen@gmail.com

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
• P. Chudoba, et al., Activation Measurements of Cross Sections for Ground and Isomeric States Production in Neutron Threshold Reactions on Y and Au, Nuclear Science and Engineering 191 (2018) 150-160
• M. Schulc, et al., Constraining high energy tail of ²³⁵U(n_th,f) prompt fission neutron spectrum, Applied Radiation and Isotopes 166 (2020) 109313
• M. Schulc, et al., Measurement of very high threshold reactions using 252Cf source, Applied Radiation and Isotopes 166 (2020) 109355

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

Request ID	94		Type of the request	Special Purpose Quantity
Target	Reaction and process	Incident Energy	Secondary energy or angle	Target uncertainty	Covariance
27-CO-59	(n,xn) x=3-5 SIG	20MeV/Thr.-150 MeV		5-10	Y
Field	Subfield	Date Request created	Date Request accepted	Ongoing action
Dosimetry	High-energy	06-OCT-17	06-OCT-17

Requester: Dr Stanislav SIMAKOV at KIT, GER
Email: intersurfen@gmail.com

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

• A. Trkov et al., IRDFF-II: A New Neutron Metrology Library, Nuclear Data Sheets 163 (2020) 1

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

Request ID	96		Type of the request	Special Purpose Quantity
Target	Reaction and process	Incident Energy	Secondary energy or angle	Target uncertainty	Covariance
57-LA-139	(n,xn) x=4-10 SIG	Threshold-150 MeV		5-10	Y
Field	Subfield	Date Request created	Date Request accepted	Ongoing action
Dosimetry	High-energy	06-OCT-17	06-OCT-17

Requester: Dr Stanislav SIMAKOV at KIT, GER
Email: intersurfen@gmail.com

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 ID	95		Type of the request	Special Purpose Quantity
Target	Reaction and process	Incident Energy	Secondary energy or angle	Target uncertainty	Covariance
45-RH-103	(n,xn) x=4-8 SIG	Threshold-150 MeV		5-10	Y
Field	Subfield	Date Request created	Date Request accepted	Ongoing action
Dosimetry	High-energy	06-OCT-17	06-OCT-17

Requester: Dr Stanislav SIMAKOV at KIT, GER
Email: intersurfen@gmail.com

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