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 GAT, USA
Email:
Project (context): Structural material for fusion power reactors
Impact:
SiC is a potential very low activation structural material for a fusion power reactor. Al-27 produced from neutron irradiation of Si generates Al-26 via the Al-27(n,2n) reaction. Al-26 is a long-lived radionuclide with a half life of 720,000 years emitting high energy gammas. The concentration of Al-26 in SiC determines whether the decommissioned fusion blanket qualifies for recycling.
Accuracy:
The request for 20% accuracy is based on what seemed feasible for the nuclear data community to achieve and probably would be sufficient for applications as well. It is not based on any sensitivity calculations.
Justification document:
The estimates consider waste generated by four full power years at 5 MW/m2 neutron wall load and are based on a particular scenario for waste handling using evaluations for Si-28(n,x)Al-27 provided by ENDF/B-VI and ADL-3 which are adopted in FENDL/A-2.0. Estimated concentration limits for Si are a factor 10 higher than earlier estimates, so that SiC would qualify as a truly low-activation material. The request asks for experimental data to validate these estimates and a subsequent re-evaluation. No direct experimental data exist.
Reference 1: E.T.Cheng, Jour. Nucl. Mat.,258-263(1998)1767
Reference 2: E.T. Cheng, Proc. of the Int. Conf. on Nuclear Data for Science and Technology, eds. G. Reffo, A. Ventura and C. Grandi, SIF, Bologna, 1158 (1997)
Comment from requester:
Two methods to measure this reaction cross section have been suggested by Herbert Vonach and others. These include (1) Measurement of Na24 activity with high-purity Si samples and intense neutron sources, and (2) Measurement of total production in Si and then subtracting the well known (n,p) cross sections to obtain the (n,n'p) values. An attempt to measure this cross section data at 14 MeV a few years ago failed due to the contamination of the Si samples with the impurity Al. The request for 20% accuracy is based on what seemed feasible for the nuclear data community to achieve and probably would be sufficient for applications as well. It is not based on any sensitivity calculations.
Review comment:
The accuracy is not known. Estimates from present and earlier evaluations differ by a factor of ten.
The request appears to imply application to post-ITER fusion reactors in view of the high neutron dose required to generate relevant quantities of Al-26.
Reference [1] refers primarily to the Si-28(n,np) reaction, whereas the production of Al-27 from Si-28 is important. This therefore also implies the (n,d) reaction since the respective thresholds are 12 and 9.7 MeV.
Quantitative information is supplied that seems to suggest directly that 20% accuracy is of interest to the application. Stoichiometric SiC has 70 wt% of Si, whereas the scenario assumed for the estimates of Ref. [1] results in an upper limit of 85 wt% Si for recycling.
This request qualifies as a General request primarily since the project end time is unspecified.
Entry Status:
Completed (as of SG-C review of May 2018) - Development in state-of-the-art nuclear reaction codes such as TALYS and EMPIRE allowed to fulfil this request. The uncertainties in the main evaluated files (ENDF/B-VIII.0, JEFF-3.3, TENDL-2015) are all consistent above the threshold reaction and vary within a 15-25% band between 13 MeV and 20 MeV.
Main references:
Please report any missing information to hprlinfo@oecd-nea.org
Experiments
Theory/Evaluation
- 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 | 6 |
Type of the request | General request |
Target | Reaction and process | Incident Energy | Secondary energy or angle | Target uncertainty | Covariance |
92-U-233 | (n,g) SIG | 10 keV-1.0 MeV | | 9 | Y |
Field | Subfield | Date Request created | Date Request accepted | Ongoing action |
Fission | Fast reactors | 28-APR-06 | 13-MAR-07 | Y |
Requester: Dr Gilles NOGUERE at CAD-DER, FR
Email: gilles.noguere@cea.fr
Project (context): JEFF
Impact:
U-233 is the main isotope of relevance to the Th/U fuel cycle. Its most important cross section is the fission cross section. The direct impact of the U-233 capture cross section is rather limited on most reactor related parameters but breeding. However, reliable capture data are needed for the evaluation work.
Accuracy:
The target accuracy on the capture cross section in the unresolved resonance range should be better than 10%
Justification document:
Interpretations of the Profil and Profil-2 experiments [1] performed in the fast reactor Phenix of the CEA Marcoule have shown an underestimation of 9% the U-233 effective capture cross section available in the latest version of the European library JEFF-3.1. The accuracy of the capture data available in EXFOR is not suitable to perform a new evaluation.
References:
[1] J. Tommasi, E. Dupont and P. Marimbeau., "Analysis of Sample Irradiation Experiments in Phénix for JEFF-3.0 Nuclear Data Validation", Nucl. Sci. Eng. 154 (2006) 119-133
[2] J.C.Hopkins and B.C.Diven, "Neutron capture to fission ratios in U-233, U-235, Pu-239", Nucl. Sci. Eng. 12 (1962)169
[3] G. Noguere, E. Dupont, J. Tommasi and D. Bernard, "Nuclear data needs for actinides by comparison with post irradiation experiments", Technical note CEA Cadarache, NT-SPRC/LEPH-05/204 (2005) (see below).
Comment from requester:
Review comment:
Owing to the difficulty in measuring the U-233(n,g) cross section, new evaluation has to take into account the Profil results [3]. Owing to the integral trend given by the interpretation of PROFIL, the final accuracy on the effective capture cross section should be lower than 9%.
Adrien Bidaud, CENBG, Bordeaux, independently investigated the sensitivity of the regeneration of U-233 to various cross sections. Sensitivities were evaluated considering a molten salt reactor under the constraints of criticality and isotopic equilibrium. Large sensitivities are observed for the capture cross section and for nu-bar. He concludes that "Any effort done to confirm the neutron yields and the capture cross section or at least to confirm their uncertainty would be very much appreciated." The energy range of interest is below that of the current request.
Entry Status:
Work in progress (as of SG-C review of May 2018)
Main references:
Please report any missing information to hprlinfo@oecd-nea.org
Experiments
- C. Carrapico, E. Berthoumieux, et al., Neutron induced capture and fission discrimination using calorimetric shape decomposition, NIM A 704 (2013) 60-67, EXFOR 23071
- M. Bacak, et al., A compact multi-plate fission chamber for the simultaneous measurement of 233U capture and fission cross-sections, ND2016, EPJ Conferences 146 (2017) 03027
Theory/Evaluation
- A. Trkov, et al., Evaluated nuclear data for nuclides within the Thorium-Uranium fuel cycle, IAEA Report STI/PUB/1435, 2010
Additional file attached:
Additional file attached:NT-Profil.pdf
Request ID | 7 |
Type of the request | General request |
Target | Reaction and process | Incident Energy | Secondary energy or angle | Target uncertainty | Covariance |
26-FE-56 | (n,xn) SIG,DDX | 7 MeV-20 MeV | 1MeV-20MeV | 30 | |
Field | Subfield | Date Request created | Date Request accepted | Ongoing action |
Fission,ADS | Shielding, Medical, SNS | 13-JUL-06 | 16-APR-07 | |
Requester: Prof. Arjan KONING at NRGPETTEN, NED
Email:
Project (context): JEFF, Model calculations
Impact:
New double differential experimental data for the Fe(n,xn) reaction will allow a crucial test of the pre-equilibrium models underlying neutron transport libraries for spallation neutron sources. They will thereby enhance the confidence in neutron transport calculations for spallation neutron sources such as envisioned for accelerator driven systems.
Accuracy:
30% for the double-differential spectra
Justification document:
A global pre-equilibrium analysis from 7 to 200 MeV based on the optical model potential, A.J. Koning and M.C. Duijvestijn,
Nucl. Phys. A744, 15 (2004).
Comment from requester:
There are hundreds of (p,xp) and (p,xn) spectra in the 20-200 MeV range available, several (n,xp) spectra, but there are basically no
double-differential (n,xn) spectra available. The presence of such data would heavily constrain the pre-equilibrium model parameters and thereby result in a much better prediction of neutron-induced spectra in the entire 50-200 MeV range. Since high-energy spectra are rather structureless the choice of target is less essential.
Review comment:
Entry Status:
Completed (as of SG-C review of May 2018) - The experimental program performed at Uppsala [Sagrado:2011] combined with improvements in nuclear reaction models allow modern evaluations to address this request, see e.g. [Herman:2018].
Main references:
Please report any missing information to hprlinfo@oecd-nea.org
Experiments
- I.C. Sagrado Garcia et al., Neutron production in neutron-induced reactions at 96 MeV on 56Fe and 208Pb, PRC 84 (2011) 044619
Theory/Evaluation
- M. Herman et al., Evaluation of Neutron Reactions on Iron Isotopes for CIELO and ENDF/B-VIII.0, NDS 148 (2018) 214
Additional file attached:
Additional file attached:
Request ID | 9 |
Type of the request | General request |
Target | Reaction and process | Incident Energy | Secondary energy or angle | Target uncertainty | Covariance |
92-U-233 | (n,g) nubar,SIG | Thermal-10 keV | | .5 | Y |
Field | Subfield | Date Request created | Date Request accepted | Ongoing action |
Fission | Molten Salt Reactors | 19-APR-07 | 19-APR-07 | Y |
Requester: Dr Adrien BIDAUD at LPSC, FR
Email: bidaud@lpsc.in2p3.fr
Project (context): JEFF
Impact:
U-233 is the main isotope of relevance to the Th/U fuel cycle. The present request concerns the viability of Th/U fueled molten salt reactors which requires that the amount of U-233 generated equals that which is destroyed.
Accuracy:
0.5% in nubar, 5% for the (n,g) cross section
Justification document:
Uncertainties on the predicted regeneration gain inferred from the uncertainties of the nuclear data have been estimated showing a 4200 pcm uncertainty for a regeneration gain designed to be 200 pcm, i.e. very close to a complete balancing of production and destruction of U-233. The main culprits are nubar contributing 2200 pcm and the capture cross section contributing 3260 pcm. A target accuracy of 2000 pcm is required to facilitate defining the reprocessing scheme for a molten salt reactor.
Reference:
A. Bidaud, Impact of Nuclear Data Uncertainties on a GEN IV Thorium Reactor at Equilibrium (attached document).
CEA Technical Note NT-SPRC/LEPH-05/204, G. Noguere et al (attachment 2).
Comment from requester:
Owing to the difficulty in measuring the U-233(n,g) cross section, a new evaluation could be done on the basis of the Profil results (see CEA Technical Note NT-SPRC/LEPH-05/204).
Review comment:
Any effort done to reduce the uncertainties on neutron yields and capture cross section down to less than 1% and about 5% respectively or at least to confirm their uncertaast fission, fusion, medical
06-OCT-17 | 06-OCT-17 | |
Requester: Dr Stanislav SIMAKOV at KARLSRUHE, GER
Email: stanislav.simakov@partner.kit.edu
Project (context): IRDFF project
Impact:
The International Reactor Dosimetry and Fusion File (IRDFF) aims at providing evaluated neutron dosimetry reactions validated for all applications related to fission reactors and fusion technology development [IAEA2017].
Accuracy:
2%-5%
Justification document:
Accurate cross sections as well as spectrum-averaged cross sections (SACS) in relevant and well-characterized neutron fields are essential for improvement and validation of the evaluated data [Simakov2017].
Comment from requester:
Measurements of the spectrum-averaged cross section are missing for validation purposes.
References
- [IAEA2017] IAEA CRP on Testing and Improving the International Reactor Dosimetry and Fusion File (IRDFF),
http://www-nds.iaea.org/IRDFFtest/.
- [Simakov2017] S. Simakov, et al., “Proposals for new measurements for IRDFF community and HPRL”, September 2017.
Review comment:
Entry Status:
Work in progress (as of SG-C review of May 2018)
Main references:
Please report any missing information to hprlinfo@oecd-nea.org
Theory/Evaluation
Additional file attached:Simakov2017.pdf
Additional file attached:
Request ID | 49 |
Type of the request | Special Purpose Quantity |
Target | Reaction and process | Incident Energy | Secondary energy or angle | Target uncertainty | Covariance |
42-MO-92 | (n,p)Nb-92m SIG,SPA | 252Cf(sf) | | 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: Dr Stanislav SIMAKOV at KARLSRUHE, GER
Email: stanislav.simakov@partner.kit.edu
Project (context): IRDFF project
Impact:
The International Reactor Dosimetry and Fusion File (IRDFF) aims at providing evaluated neutron dosimetry reactions validated for all applications related to fission reactors and fusion technology development [IAEA2017].
Accuracy:
2%-5%
Justification document:
Accurate cross sections as well as spectrum-averaged cross sections (SACS) in relevant and well-characterized neutron fields are essential for improvement and validation of the evaluated data [Simakov2017].
Comment from requester:
New measurements of the spectrum-averaged cross section are requested to solve C/E discrepancy. See SPA_CE_Cf252.pdf below.
References
- [IAEA2017] IAEA CRP on Testing and Improving the International Reactor Dosimetry and Fusion File (IRDFF),
http://www-nds.iaea.org/IRDFFtest/.
- [Simakov2017] S. Simakov, et al., “Proposals for new measurements for IRDFF community and HPRL”, September 2017.
Review comment:
Entry Status:
Work in progress (as of SG-C review of May 2018)
Main references:
Please report any missing information to hprlinfo@oecd-nea.org
Theory/Evaluation
Additional file attached:Simakov2017.pdf
Additional file attached:SPA_CE_Cf252.pdf
Request ID | 50 |
Type of the request | Special Purpose Quantity |
Target | Reaction and process | Incident Energy | Secondary energy or angle | Target uncertainty | Covariance |
28-NI-60 | (n,p) SIG,SPA | 252Cf(sf) | | 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: Dr Stanislav SIMAKOV at KARLSRUHE, GER
Email: stanislav.simakov@partner.kit.edu
Project (context): IRDFF project
Impact:
The International Reactor Dosimetry and Fusion File (IRDFF) aims at providing evaluated neutron dosimetry reactions validated for all applications related to fission reactors and fusion technology development [IAEA2017].
Accuracy:
2%-5%
Justification document:
Accurate cross sections as well as spectrum-averaged cross sections (SACS) in relevant and well-characterized neutron fields are essential for improvement and validation of the evaluated data [Simakov2017].
Comment from requester:
New measurements of the spectrum-averaged cross section are requested to solve C/E discrepancy. See SPA_CE_Cf252.pdf below.
References
- [IAEA2017] IAEA CRP on Testing and Improving the International Reactor Dosimetry and Fusion File (IRDFF),
http://www-nds.iaea.org/IRDFFtest/.
- [Simakov2017] S. Simakov, et al., “Proposals for new measurements for IRDFF community and HPRL”, September 2017.
Review comment:
Entry Status:
Work in progress (as of SG-C review of May 2018)
Main references:
Please report any missing information to hprlinfo@oecd-nea.org
Experiments
Theory/Evaluation
Additional file attached:Simakov2017.pdf
Additional file attached:SPA_CE_Cf252.pdf
Request ID | 51 |
Type of the request | Special Purpose Quantity |
Target | Reaction and process | Incident Energy | Secondary energy or angle | Target uncertainty | Covariance |
26-FE-54 | (n,a) SIG,SPA | 252Cf(sf) | | 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: Dr Stanislav SIMAKOV at KARLSRUHE, GER
Email: stanislav.simakov@partner.kit.edu
Project (context): IRDFF project
Impact:
The International Reactor Dosimetry and Fusion File (IRDFF) aims at providing evaluated neutron dosimetry reactions validated for all applications related to fission reactors and fusion technology development [IAEA2017].
Accuracy:
2%-5%
Justification document:
Accurate cross sections as well as spectrum-averaged cross sections (SACS) in relevant and well-characterized neutron fields are essential for improvement and validation of the evaluated data [Simakov2017].
Comment from requester:
Measurements of the spectrum-averaged cross section are missing for validation purposes, especially for improvement of the prompt fission neutron spectrum at high energy. See Cf252U235_HighThreshold.pdf below.
References
- [IAEA2017] IAEA CRP on Testing and Improving the International Reactor Dosimetry and Fusion File (IRDFF),
http://www-nds.iaea.org/IRDFFtest/.
- [Simakov2017] S. Simakov, et al., “Proposals for new measurements for IRDFF community and HPRL”, September 2017.
Review comment:
Entry Status:
Work in progress (as of SG-C review of May 2018)
Main references:
Please report any missing information to hprlinfo@oecd-nea.org
Experiments
Theory/Evaluation
Validation
Additional file attached:Simakov2017.pdf
Additional file attached:Cf252U235_HighThreshold.pdf
Request ID | 52 |
Type of the request | Special Purpose Quantity |
Target | Reaction and process | Incident Energy | Secondary energy or angle | Target uncertainty | Covariance |
33-AS-75 | (n,2n) SIG,SPA | 252Cf(sf) | | 2-5 | Y |
Field | Subfield | Date Request created | Date Request accepted | Ongoing action |
Dosimetry | D-T fusion | 06-OCT-17 | 06-OCT-17 | |
Requester: Dr Stanislav SIMAKOV at KARLSRUHE, GER
Email: stanislav.simakov@partner.kit.edu
Project (context): IRDFF project
Impact:
The International Reactor Dosimetry and Fusion File (IRDFF) aims at providing evaluated neutron dosimetry reactions validated for all applications related to fission reactors and fusion technology development [IAEA2017].
Accuracy:
2%-5%
Justification document:
Accurate cross sections as well as spectrum-averaged cross sections (SACS) in relevant and well-characterized neutron fields are essential for improvement and validation of the evaluated data [Simakov2017].
Following a recommendation from the IAEA Data Development Project on Neutron Standards [Pronyaev2013], the IRDFF project supports SACS measurements of high-threshold (above 10 MeV) dosimetry cross-sections in well-characterized 252Cf(sf) and 235U(nth,f) neutron fields in order to improve the cross sections and/or the high-energy part of the prompt fission neutron spectra.
Comment from requester:
Measurements of the spectrum-averaged cross section are missing for validation purposes and for improvement of the cross section and prompt fission neutron spectrum above 10 MeV. See Cf252U235_HighThreshold.pdf below.
References
- [IAEA2017] IAEA CRP on Testing and Improving the International Reactor Dosimetry and Fusion File (IRDFF),
http://www-nds.iaea.org/IRDFFtest/.
- [Simakov2017] S. Simakov, et al., “Proposals for new measurements for IRDFF community and HPRL”, September 2017.
- [Pronyaev2013] V.G. Pronyaev, A.D. Carlson and R. Capote Noy, “Toward a New Evaluation of Neutron Standards”, IAEA Technical Meeting, 8-12 July 2013, INDC(NDS)-0641.
Review comment:
Entry Status:
Work in progress (as of SG-C review of May 2018)
Main references:
Please report any missing information to hprlinfo@oecd-nea.org
Theory/Evaluation
Additional file attached:Simakov2017.pdf
Additional file attached:Cf252U235_HighThreshold.pdf
Request ID | 53 |
Type of the request | Special Purpose Quantity |
Target | Reaction and process | Incident Energy | Secondary energy or angle | Target uncertainty | Covariance |
39-Y-89 | (n,2n) SIG,SPA | 252Cf(sf) | | 2-5 | Y |
Field | Subfield | Date Request created | Date Request accepted | Ongoing action |
Dosimetry | D-T fusion | 06-OCT-17 | 06-OCT-17 | |
Requester: Dr Stanislav SIMAKOV at KARLSRUHE, GER
Email: stanislav.simakov@partner.kit.edu
Project (context): IRDFF project
Impact:
The International Reactor Dosimetry and Fusion File (IRDFF) aims at providing evaluated neutron dosimetry reactions validated for all applications related to fission reactors and fusion technology development [IAEA2017].
Accuracy:
2%-5%
Justification document:
Accurate cross sections as well as spectrum-averaged cross sections (SACS) in relevant and well-characterized neutron fields are essential for improvement and validation of the evaluated data [Simakov2017].
Following a recommendation from the IAEA Data Development Project on Neutron Standards [Pronyaev2013], the IRDFF project supports SACS measurements of high-threshold (above 10 MeV) dosimetry cross-sections in well-characterized 252Cf(sf) and 235U(nth,f) neutron fields in order to improve the cross sections and/or the high-energy part of the prompt fission neutron spectra.
Comment from requester:
Measurements of the spectrum-averaged cross section are missing for validation purposes and for improvement of the cross section and prompt fission neutron spectrum above 10 MeV. See Cf252U235_HighThreshold.pdf below.
References
- [IAEA2017] IAEA CRP on Testing and Improving the International Reactor Dosimetry and Fusion File (IRDFF),
http://www-nds.iaea.org/IRDFFtest/.
- [Simakov2017] S. Simakov, et al., “Proposals for new measurements for IRDFF community and HPRL”, September 2017.
- [Pronyaev2013] V.G. Pronyaev, A.D. Carlson and R. Capote Noy, “Toward a New Evaluation of Neutron Standards”, IAEA Technical Meeting, 8-12 July 2013, INDC(NDS)-0641.
Review comment:
Entry Status:
Work in progress (as of SG-C review of May 2018)
Main references:
Please report any missing information to hprlinfo@oecd-nea.org
Experiments
Theory/Evaluation
Validation
Additional file attached:Simakov2017.pdf
Additional file attached:Cf252U235_HighThreshold.pdf
Request ID | 54 |
Type of the request | Special Purpose Quantity |
Target | Reaction and process | Incident Energy | Secondary energy or angle | Target uncertainty | Covariance |
25-MN-55 | (n,g) SIG,SPA | 235U(n,f) | | 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: Dr Stanislav SIMAKOV at KARLSRUHE, GER
Email: stanislav.simakov@partner.kit.edu
Project (context): IRDFF project
Impact:
The International Reactor Dosimetry and Fusion File (IRDFF) aims at providing evaluated neutron dosimetry reactions validated for all applications related to fission reactors and fusion technology development [IAEA2017].
Accuracy:
2%-5%
Justification document:
Accurate cross sections as well as spectrum-averaged cross sections (SACS) in relevant and well-characterized neutron fields are essential for improvement and validation of the evaluated data [Simakov2017].
Comment from requester:
New measurements of the spectrum-averaged cross section are requested to solve C/E discrepancy. See SPA_CE_U235.pdf below.
References
- [IAEA2017] IAEA CRP on Testing and Improving the International Reactor Dosimetry and Fusion File (IRDFF),
http://www-nds.iaea.org/IRDFFtest/.
- [Simakov2017] S. Simakov, et al., “Proposals for new measurements for IRDFF community and HPRL”, September 2017.
Review comment:
Non-threshold reactions measured in fast spectra such as the 252Cf(sf) and 235U(nth,f) spectrum tend to have their spectrum averaged cross section dominated by scattering contributions and ‘room-return’ neutrons. Experiments should be designed to minimize these contributions and maximize the reaction rate from the primary source. For new experiments best estimates must be provided by detailed Monte Carlo calculation of the spectrum realized in the experiment and the Monte Carlo model must be made available to IRDFF to facilitate validation of new proposals for the cross section. In all cases it is advised to publish both the fully corrected SACS and the measured reaction rates of the primary reaction and the monitor reactions used for normalization and validation of the model. The measured reaction rates must be provided with a full covariance matrix.
Entry Status:
Work in progress (as of SG-C review of May 2018)
Main references:
Please report any missing information to hprlinfo@oecd-nea.org
Theory/Evaluation
Additional file attached:Simakov2017.pdf
Additional file attached:SPA_CE_U235.pdf
Request ID | 55 |
Type of the request | Special Purpose Quantity |
Target | Reaction and process | Incident Energy | Secondary energy or angle | Target uncertainty | Covariance |
92-U-238 | (n,g) SIG,SPA | 235U(n,f) | | 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: Dr Stanislav SIMAKOV at KARLSRUHE, GER
Email: stanislav.simakov@partner.kit.edu
Project (context): IRDFF project
Impact:
The International Reactor Dosimetry and Fusion File (IRDFF) aims at providing evaluated neutron dosimetry reactions validated for all applications related to fission reactors and fusion technology development [IAEA2017].
Accuracy:
2%-5%
Justification document:
Accurate cross sections as well as spectrum-averaged cross sections (SACS) in relevant and well-characterized neutron fields are essential for improvement and validation of the evaluated data [Simakov2017].
Comment from requester:
New measurements of the spectrum-averaged cross section are requested to solve C/E discrepancy. See SPA_CE_U235.pdf below.
References
- [IAEA2017] IAEA CRP on Testing and Improving the International Reactor Dosimetry and Fusion File (IRDFF),
http://www-nds.iaea.org/IRDFFtest/.
- [Simakov2017] S. Simakov, et al., “Proposals for new measurements for IRDFF community and HPRL”, September 2017.
Review comment:
Non-threshold reactions measured in fast spectra such as the 252Cf(sf) and 235U(nth,f) spectrum tend to have their spectrum averaged cross section dominated by scattering contributions and ‘room-return’ neutrons. Experiments should be designed to minimize these contributions and maximize the reaction rate from the primary source. For new experiments best estimates must be provided by detailed Monte Carlo calculation of the spectrum realized in the experiment and the Monte Carlo model must be made available to IRDFF to facilitate validation of new proposals for the cross section. In all cases it is advised to publish both the fully corrected SACS and the measured reaction rates of the primary reaction and the monitor reactions used for normalization and validation of the model. The measured reaction rates must be provided with a full covariance matrix.
Entry Status:
Work in progress (as of SG-C review of May 2018)
Main references:
Please report any missing information to hprlinfo@oecd-nea.org
Theory/Evaluation
Additional file attached:Simakov2017.pdf
Additional file attached:SPA_CE_U235.pdf
Request ID | 56 |
Type of the request | Special Purpose Quantity |
Target | Reaction and process | Incident Energy | Secondary energy or angle | Target uncertainty | Covariance |
29-CU-63 | (n,g) SIG,SPA | 235U(n,f) | | 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: Dr Stanislav SIMAKOV at KARLSRUHE, GER
Email: stanislav.simakov@partner.kit.edu
Project (context): IRDFF project
Impact:
The International Reactor Dosimetry and Fusion File (IRDFF) aims at providing evaluated neutron dosimetry reactions validated for all applications related to fission reactors and fusion technology development [IAEA2017].
Accuracy:
2%-5%
Justification document:
Accurate cross sections as well as spectrum-averaged cross sections (SACS) in relevant and well-characterized neutron fields are essential for improvement and validation of the evaluated data [Simakov2017].
Comment from requester:
New measurements of the spectrum-averaged cross section are requested to solve C/E discrepancy. See SPA_CE_U235.pdf below.
References
- [IAEA2017] IAEA CRP on Testing and Improving the International Reactor Dosimetry and Fusion File (IRDFF),
http://www-nds.iaea.org/IRDFFtest/.
- [Simakov2017] S. Simakov, et al., “Proposals for new measurements for IRDFF community and HPRL”, September 2017.
Review comment:
Non-threshold reactions measured in fast spectra such as the 252Cf(sf) and 235U(nth,f) spectrum tend to have their spectrum averaged cross section dominated by scattering contributions and ‘room-return’ neutrons. Experiments should be designed to minimize these contributions and maximize the reaction rate from the primary source. For new experiments best estimates must be provided by detailed Monte Carlo calculation of the spectrum realized in the experiment and the Monte Carlo model must be made available to IRDFF to facilitate validation of new proposals for the cross section. In all cases it is advised to publish both the fully corrected SACS and the measured reaction rates of the primary reaction and the monitor reactions used for normalization and validation of the model. The measured reaction rates must be provided with a full covariance matrix.
Entry Status:
Work in progress (as of SG-C review of May 2018)
Main references:
Please report any missing information to hprlinfo@oecd-nea.org
Theory/Evaluation
Additional file attached:Simakov2017.pdf
Additional file attached:SPA_CE_U235.pdf
Request ID | 57 |
Type of the request | Special Purpose Quantity |
Target | Reaction and process | Incident Energy | Secondary energy or angle | Target uncertainty | Covariance |
57-LA-139 | (n,g) SIG,SPA | 235U(n,f) | | 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: Dr Stanislav SIMAKOV at KARLSRUHE, GER
Email: stanislav.simakov@partner.kit.edu
Project (context): IRDFF project
Impact:
The International Reactor Dosimetry and Fusion File (IRDFF) aims at providing evaluated neutron dosimetry reactions validated for all applications related to fission reactors and fusion technology development [IAEA2017].
Accuracy:
2%-5%
Justification document:
Accurate cross sections as well as spectrum-averaged cross sections (SACS) in relevant and well-characterized neutron fields are essential for improvement and validation of the evaluated data [Simakov2017].
Comment from requester:
New measurements of the spectrum-averaged cross section are requested to solve C/E discrepancy. See SPA_CE_U235.pdf below.
References
- [IAEA2017] IAEA CRP on Testing and Improving the International Reactor Dosimetry and Fusion File (IRDFF),
http://www-nds.iaea.org/IRDFFtest/.
- [Simakov2017] S. Simakov, et al., “Proposals for new measurements for IRDFF community and HPRL”, September 2017.
Review comment:
Non-threshold reactions measured in fast spectra such as the 252Cf(sf) and 235U(nth,f) spectrum tend to have their spectrum averaged cross section dominated by scattering contributions and ‘room-return’ neutrons. Experiments should be designed to minimize these contributions and maximize the reaction rate from the primary source. For new experiments best estimates must be provided by detailed Monte Carlo calculation of the spectrum realized in the experiment and the Monte Carlo model must be made available to IRDFF to facilitate validation of new proposals for the cross section. In all cases it is advised to publish both the fully corrected SACS and the measured reaction rates of the primary reaction and the monitor reactions used for normalization and validation of the model. The measured reaction rates must be provided with a full covariance matrix.
Entry Status:
Work in progress (as of SG-C review of May 2018)
Main references:
Please report any missing information to hprlinfo@oecd-nea.org
Theory/Evaluation
Additional file attached:Simakov2017.pdf
Additional file attached:SPA_CE_U235.pdf
Request ID | 58 |
Type of the request | Special Purpose Quantity |
Target | Reaction and process | Incident Energy | Secondary energy or angle | Target uncertainty | Covariance |
45-RH-103 | (n,inl)Rh-103m SIG,SPA | 235U(n,f) | | 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: Dr Stanislav SIMAKOV at KARLSRUHE, GER
Email: stanislav.simakov@partner.kit.edu
Project (context): IRDFF project
Impact:
The International Reactor Dosimetry and Fusion File (IRDFF) aims at providing evaluated neutron dosimetry reactions validated for all applications related to fission reactors and fusion technology development [IAEA2017].
Accuracy:
2%-5%
Justification document:
Accurate cross sections as well as spectrum-averaged cross sections (SACS) in relevant and well-characterized neutron fields are essential for improvement and validation of the evaluated data [Simakov2017].
Comment from requester:
New measurements of the spectrum-averaged cross section are requested to solve C/E discrepancy. See SPA_CE_U235.pdf below.
References
- [IAEA2017] IAEA CRP on Testing and Improving the International Reactor Dosimetry and Fusion File (IRDFF),
http://www-nds.iaea.org/IRDFFtest/.
- [Simakov2017] S. Simakov, et al., “Proposals for new measurements for IRDFF community and HPRL”, September 2017.
Review comment:
Entry Status:
Work in progress (as of SG-C review of May 2018)
Main references:
Please report any missing information to hprlinfo@oecd-nea.org
Experiments
Theory/Evaluation
Additional file attached:Simakov2017.pdf
Additional file attached:SPA_CE_U235.pdf
Request ID | 59 |
Type of the request | Special Purpose Quantity |
Target | Reaction and process | Incident Energy | Secondary energy or angle | Target uncertainty | Covariance |
69-TM-169 | (n,2n) SIG,SPA | 235U(n,f) | | 2-5 | Y |
Field | Subfield | Date Request created | Date Request accepted | Ongoing action |
Dosimetry | D-T fusion | 06-OCT-17 | 06-OCT-17 | |
Requester: Dr Stanislav SIMAKOV at KARLSRUHE, GER
Email: stanislav.simakov@partner.kit.edu
Project (context): IRDFF project
Impact:
The International Reactor Dosimetry and Fusion File (IRDFF) aims at providing evaluated neutron dosimetry reactions validated for all applications related to fission reactors and fusion technology development [IAEA2017].
Accuracy:
2%-5%
Justification document:
Accurate cross sections as well as spectrum-averaged cross sections (SACS) in relevant and well-characterized neutron fields are essential for improvement and validation of the evaluated data [Simakov2017].
Following a recommendation from the IAEA Data Development Project on Neutron Standards [Pronyaev2013], the IRDFF project supports SACS measurements of high-threshold (above 10 MeV) dosimetry cross-sections in well-characterized 252Cf(sf) and 235U(nth,f) neutron fields in order to improve the cross sections and/or the high-energy part of the prompt fission neutron spectra.
Comment from requester:
New measurements of the spectrum-averaged cross section are requested to solve C/E discrepancy and for improvement of the cross section and prompt fission neutron spectrum above 10 MeV. See CE_U235_and_HighThreshold.pdf below.
References
- [IAEA2017] IAEA CRP on Testing and Improving the International Reactor Dosimetry and Fusion File (IRDFF),
http://www-nds.iaea.org/IRDFFtest/.
- [Simakov2017] S. Simakov, et al., “Proposals for new measurements for IRDFF community and HPRL”, September 2017.
- [Pronyaev2013] V.G. Pronyaev, A.D. Carlson and R. Capote Noy, “Toward a New Evaluation of Neutron Standards”, IAEA Technical Meeting, 8-12 July 2013, INDC(NDS)-0641.
Review comment:
Entry Status:
Work in progress (as of SG-C review of May 2018)
Main references:
Please report any missing information to hprlinfo@oecd-nea.org
Theory/Evaluation
Additional file attached:Simakov2017.pdf
Additional file attached:CE_U235_and_HighThreshold.pdf
Request ID | 60 |
Type of the request | Special Purpose Quantity |
Target | Reaction and process | Incident Energy | Secondary energy or angle | Target uncertainty | Covariance |
29-CU-65 | (n,2n) SIG,SPA | 235U(n,f) | | 2-5 | Y |
Field | Subfield | Date Request created | Date Request accepted | Ongoing action |
Dosimetry | D-T fusion | 06-OCT-17 | 06-OCT-17 | |
Requester: Dr Stanislav SIMAKOV at KARLSRUHE, GER
Email: stanislav.simakov@partner.kit.edu
Project (context): IRDFF project
Impact:
The International Reactor Dosimetry and Fusion File (IRDFF) aims at providing evaluated neutron dosimetry reactions validated for all applications related to fission reactors and fusion technology development [IAEA2017].
Accuracy:
2%-5%
Justification document:
Accurate cross sections as well as spectrum-averaged cross sections (SACS) in relevant and well-characterized neutron fields are essential for improvement and validation of the evaluated data [Simakov2017].
Following a recommendation from the IAEA Data Development Project on Neutron Standards [Pronyaev2013], the IRDFF project supports SACS measurements of high-threshold (above 10 MeV) dosimetry cross-sections in well-characterized 252Cf(sf) and 235U(nth,f) neutron fields in order to improve the cross sections and/or the high-energy part of the prompt fission neutron spectra.
Comment from requester:
Measurements of the spectrum-averaged cross section are missing for validation purposes and for improvement of the cross section and prompt fission neutron spectrum above 10 MeV. See Cf252U235_HighThreshold.pdf below.
References
- [IAEA2017] IAEA CRP on Testing and Improving the International Reactor Dosimetry and Fusion File (IRDFF),
http://www-nds.iaea.org/IRDFFtest/.
- [Simakov2017] S. Simakov, et al., “Proposals for new measurements for IRDFF community and HPRL”, September 2017.
- [Pronyaev2013] V.G. Pronyaev, A.D. Carlson and R. Capote Noy, “Toward a New Evaluation of Neutron Standards”, IAEA Technical Meeting, 8-12 July 2013, INDC(NDS)-0641.
Review comment:
Entry Status:
Work in progress (as of SG-C review of May 2018)
Main references:
Please report any missing information to hprlinfo@oecd-nea.org
Theory/Evaluation
Additional file attached:Simakov2017.pdf
Additional file attached:Cf252U235_HighThreshold.pdf
Request ID | 61 |
Type of the request | Special Purpose Quantity |
Target | Reaction and process | Incident Energy | Secondary energy or angle | Target uncertainty | Covariance |
25-MN-55 | (n,2n) SIG,SPA | 235U(n,f) | | 2-5 | Y |
Field | Subfield | Date Request created | Date Request accepted | Ongoing action |
Dosimetry | D-T fusion | 06-OCT-17 | 06-OCT-17 | |
Requester: Dr Stanislav SIMAKOV at KARLSRUHE, GER
Email: stanislav.simakov@partner.kit.edu
Project (context): IRDFF project
Impact:
The International Reactor Dosimetry and Fusion File (IRDFF) aims at providing evaluated neutron dosimetry reactions validated for all applications related to fission reactors and fusion technology development [IAEA2017].
Accuracy:
2%-5%
Justification document:
Accurate cross sections as well as spectrum-averaged cross sections (SACS) in relevant and well-characterized neutron fields are essential for improvement and validation of the evaluated data [Simakov2017].
Following a recommendation from the IAEA Data Development Project on Neutron Standards [Pronyaev2013], the IRDFF project supports SACS measurements of high-threshold (above 10 MeV) dosimetry cross-sections in well-characterized 252Cf(sf) and 235U(nth,f) neutron fields in order to improve the cross sections and/or the high-energy part of the prompt fission neutron spectra.
Comment from requester:
New measurements of the spectrum-averaged cross section are requested to solve C/E discrepancy and for improvement of the cross section and prompt fission neutron spectrum above 10 MeV. See SPA_CE_U235.pdf below.
References
- [IAEA2017] IAEA CRP on Testing and Improving the International Reactor Dosimetry and Fusion File (IRDFF),
http://www-nds.iaea.org/IRDFFtest/.
- [Simakov2017] S. Simakov, et al., “Proposals for new measurements for IRDFF community and HPRL”, September 2017.
- [Pronyaev2013] V.G. Pronyaev, A.D. Carlson and R. Capote Noy, “Toward a New Evaluation of Neutron Standards”, IAEA Technical Meeting, 8-12 July 2013, INDC(NDS)-0641.
Review comment:
Entry Status:
Work in progress (as of SG-C review of May 2018)
Main references:
Please report any missing information to hprlinfo@oecd-nea.org
Experiments
Theory/Evaluation
Additional file attached:Simakov2017.pdf
Additional file attached:SPA_CE_U235.pdf
Request ID | 62 |
Type of the request | Special Purpose Quantity |
Target | Reaction and process | Incident Energy | Secondary energy or angle | Target uncertainty | Covariance |
28-NI-58 | (n,2n) SIG,SPA | 235U(n,f) | | 2-5 | Y |
Field | Subfield | Date Request created | Date Request accepted | Ongoing action |
Dosimetry | D-T fusion | 06-OCT-17 | 06-OCT-17 | |
Requester: Dr Stanislav SIMAKOV at KARLSRUHE, GER
Email: stanislav.simakov@partner.kit.edu
Project (context): IRDFF project
Impact:
The International Reactor Dosimetry and Fusion File (IRDFF) aims at providing evaluated neutron dosimetry reactions validated for all applications related to fission reactors and fusion technology development [IAEA2017].
Accuracy:
2%-5%
Justification document:
Accurate cross sections as well as spectrum-averaged cross sections (SACS) in relevant and well-characterized neutron fields are essential for improvement and validation of the evaluated data [Simakov2017].
Following a recommendation from the IAEA Data Development Project on Neutron Standards [Pronyaev2013], the IRDFF project supports SACS measurements of high-threshold (above 10 MeV) dosimetry cross-sections in well-characterized 252Cf(sf) and 235U(nth,f) neutron fields in order to improve the cross sections and/or the high-energy part of the prompt fission neutron spectra.
Comment from requester:
New measurements of the spectrum-averaged cross section are requested to solve C/E discrepancy and for improvement of the cross section and prompt fission neutron spectrum above 10 MeV. See SPA_CE_U235.pdf below.
References
- [IAEA2017] IAEA CRP on Testing and Improving the International Reactor Dosimetry and Fusion File (IRDFF),
http://www-nds.iaea.org/IRDFFtest/.
- [Simakov2017] S. Simakov, et al., “Proposals for new measurements for IRDFF community and HPRL”, September 2017.
- [Pronyaev2013] V.G. Pronyaev, A.D. Carlson and R. Capote Noy, “Toward a New Evaluation of Neutron Standards”, IAEA Technical Meeting, 8-12 July 2013, INDC(NDS)-0641.
Review comment:
Entry Status:
Work in progress (as of SG-C review of May 2018)
Main references:
Please report any missing information to hprlinfo@oecd-nea.org
Theory/Evaluation
Additional file attached:Simakov2017.pdf
Additional file attached:SPA_CE_U235.pdf
Request ID | 63 |
Type of the request | Special Purpose Quantity |
Target | Reaction and process | Incident Energy | Secondary energy or angle | Target uncertainty | Covariance |
95-AM-241 | (n,f) SIG,SPA | 252Cf(sf)-235U(n,f) | | 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: Dr Stanislav SIMAKOV at KARLSRUHE, GER
Email: stanislav.simakov@partner.kit.edu
Project (context): IRDFF project
Impact:
The International Reactor Dosimetry and Fusion File (IRDFF) aims at providing evaluated neutron dosimetry reactions validated for all applications related to fission reactors and fusion technology development [IAEA2017].
Accuracy:
2%-5%
Justification document:
Accurate cross sections as well as spectrum-averaged cross sections (SACS) in relevant and well-characterized neutron fields are essential for improvement and validation of the evaluated data [Simakov2017].
Comment from requester:
Measurements of the spectrum-averaged cross section are missing for validation purposes.
References
- [IAEA2017] IAEA CRP on Testing and Improving the International Reactor Dosimetry and Fusion File (IRDFF),
http://www-nds.iaea.org/IRDFFtest/.
- [Simakov2017] S. Simakov, et al., “Proposals for new measurements for IRDFF community and HPRL”, September 2017.
Review comment:
Non-threshold reactions measured in fast spectra such as the 252Cf(sf) and 235U(nth,f) spectrum tend to have their spectrum averaged cross section dominated by scattering contributions and ‘room-return’ neutrons. Experiments should be designed to minimize these contributions and maximize the reaction rate from the primary source. For new experiments best estimates must be provided by detailed Monte Carlo calculation of the spectrum realized in the experiment and the Monte Carlo model must be made available to IRDFF to facilitate validation of new proposals for the cross section. In all cases it is advised to publish both the fully corrected SACS and the measured reaction rates of the primary reaction and the monitor reactions used for normalization and validation of the model. The measured reaction rates must be provided with a full covariance matrix.
Entry Status:
Work in progress (as of SG-C review of May 2018)
Main references:
Please report any missing information to hprlinfo@oecd-nea.org
Theory/Evaluation
Additional file attached:Simakov2017.pdf
Additional file attached:
Request ID | 64 |
Type of the request | Special Purpose Quantity |
Target | Reaction and process | Incident Energy | Secondary energy or angle | Target uncertainty | Covariance |
15-P-31 | (n,p) SIG,SPA | 252Cf(sf)-235U(n,f) | | 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: Dr Stanislav SIMAKOV at KARLSRUHE, GER
Email: stanislav.simakov@partner.kit.edu
Project (context): IRDFF project
Impact:
The International Reactor Dosimetry and Fusion File (IRDFF) aims at providing evaluated neutron dosimetry reactions validated for all applications related to fission reactors and fusion technology development [IAEA2017].
Accuracy:
2%-5%
Justification document:
Accurate cross sections as well as spectrum-averaged cross sections (SACS) in relevant and well-characterized neutron fields are essential for improvement and validation of the evaluated data [Simakov2017].
Comment from requester:
Measurements of the 252Cf(sf)-spectrum-averaged cross section are missing for validation purposes. New measurements of the 235U(n,f)-spectrum-averaged cross section are requested to solve C/E discrepancy. See SPA_CE_Cf252U235.pdf below.
References
- [IAEA2017] IAEA CRP on Testing and Improving the International Reactor Dosimetry and Fusion File (IRDFF),
http://www-nds.iaea.org/IRDFFtest/.
- [Simakov2017] S. Simakov, et al., “Proposals for new measurements for IRDFF community and HPRL”, September 2017.
Review comment:
Entry Status:
Work in progress (as of SG-C review of May 2018)
Main references:
Please report any missing information to hprlinfo@oecd-nea.org
Theory/Evaluation
Additional file attached:Simakov2017.pdf
Additional file attached:SPA_CE_Cf252U235.pdf
Request ID | 65 |
Type of the request | Special Purpose Quantity |
Target | Reaction and process | Incident Energy | Secondary energy or angle | Target uncertainty | Covariance |
92-U-238 | (n,2n) SIG,SPA | 252Cf(sf)-235U(n,f) | | 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: Dr Stanislav SIMAKOV at KARLSRUHE, GER
Email: stanislav.simakov@partner.kit.edu
Project (context): IRDFF project
Impact:
The International Reactor Dosimetry and Fusion File (IRDFF) aims at providing evaluated neutron dosimetry reactions validated for all applications related to fission reactors and fusion technology development [IAEA2017].
Accuracy:
2%-5%
Justification document:
Accurate cross sections as well as spectrum-averaged cross sections (SACS) in relevant and well-characterized neutron fields are essential for improvement and validation of the evaluated data [Simakov2017].
Comment from requester:
New measurements of the spectrum-averaged cross section are requested to solve C/E discrepancy and for improvement of the prompt fission neutron spectrum at high energy. See CE_Cf252U235_and_HighThreshold.pdf below.
References
- [IAEA2017] IAEA CRP on Testing and Improving the International Reactor Dosimetry and Fusion File (IRDFF),
http://www-nds.iaea.org/IRDFFtest/.
- [Simakov2017] S. Simakov, et al., “Proposals for new measurements for IRDFF community and HPRL”, September 2017.
Review comment:
Entry Status:
Work in progress (as of SG-C review of May 2018)
Main references:
Please report any missing information to hprlinfo@oecd-nea.org
Theory/Evaluation
Additional file attached:Simakov2017.pdf
Additional file attached:CE_Cf252U235_and_HighThreshold.pdf
Request ID | 66 |
Type of the request | Special Purpose Quantity |
Target | Reaction and process | Incident Energy | Secondary energy or angle | Target uncertainty | Covariance |
49-IN-115 | (n,2n)In-114m SIG,SPA | 252Cf(sf)-235U(n,f) | | 2-5 | Y |
Field | Subfield | Date Request created | Date Request accepted | Ongoing action |
Dosimetry | D-T fusion | 06-OCT-17 | 06-OCT-17 | |
Requester: Dr Stanislav SIMAKOV at KARLSRUHE, GER
Email: stanislav.simakov@partner.kit.edu
Project (context): IRDFF project
Impact:
The International Reactor Dosimetry and Fusion File (IRDFF) aims at providing evaluated neutron dosimetry reactions validated for all applications related to fission reactors and fusion technology development [IAEA2017].
Accuracy:
2%-5%
Justification document:
Accurate cross sections as well as spectrum-averaged cross sections (SACS) in relevant and well-characterized neutron fields are essential for improvement and validation of the evaluated data [Simakov2017].
Following a recommendation from the IAEA Data Development Project on Neutron Standards [Pronyaev2013], the IRDFF project supports SACS measurements of high-threshold (above 10 MeV) dosimetry cross-sections in well-characterized 252Cf(sf) and 235U(nth,f) neutron fields in order to improve the cross sections and/or the high-energy part of the prompt fission neutron spectra.
Comment from requester:
Measurements of the spectrum-averaged cross section are missing for validation purposes and for improvement of the cross section and prompt fission neutron spectrum above 10 MeV. See Cf252U235_HighThreshold.pdf below.
References
- [IAEA2017] IAEA CRP on Testing and Improving the International Reactor Dosimetry and Fusion File (IRDFF),
http://www-nds.iaea.org/IRDFFtest/.
- [Simakov2017] S. Simakov, et al., “Proposals for new measurements for IRDFF community and HPRL”, September 2017.
- [Pronyaev2013] V.G. Pronyaev, A.D. Carlson and R. Capote Noy, “Toward a New Evaluation of Neutron Standards”, IAEA Technical Meeting, 8-12 July 2013, INDC(NDS)-0641.
Review comment:
Entry Status:
Work in progress (as of SG-C review of May 2018)
Main references:
Please report any missing information to hprlinfo@oecd-nea.org
Theory/Evaluation
Additional file attached:Simakov2017.pdf
Additional file attached:Cf252U235_HighThreshold.pdf
Request ID | 67 |
Type of the request | Special Purpose Quantity |
Target | Reaction and process | Incident Energy | Secondary energy or angle | Target uncertainty | Covariance |
59-PR-141 | (n,2n) SIG,SPA | 252Cf(sf)-235U(n,f) | | 2-5 | Y |
Field | Subfield | Date Request created | Date Request accepted | Ongoing action |
Dosimetry | D-T fusion | 06-OCT-17 | 06-OCT-17 | |
Requester: Dr Stanislav SIMAKOV at KARLSRUHE, GER
Email: stanislav.simakov@partner.kit.edu
Project (context): IRDFF project
Impact:
The International Reactor Dosimetry and Fusion File (IRDFF) aims at providing evaluated neutron dosimetry reactions validated for all applications related to fission reactors and fusion technology development [IAEA2017].
Accuracy:
2%-5%
Justification document:
Accurate cross sections as well as spectrum-averaged cross sections (SACS) in relevant and well-characterized neutron fields are essential for improvement and validation of the evaluated data [Simakov2017].
Following a recommendation from the IAEA Data Development Project on Neutron Standards [Pronyaev2013], the IRDFF project supports SACS measurements of high-threshold (above 10 MeV) dosimetry cross-sections in well-characterized 252Cf(sf) and 235U(nth,f) neutron fields in order to improve the cross sections and/or the high-energy part of the prompt fission neutron spectra.
Comment from requester:
Measurements of the spectrum-averaged cross section are missing for validation purposes and for improvement of the cross section and prompt fission neutron spectrum above 10 MeV. See Cf252U235_HighThreshold.pdf below.
References
- [IAEA2017] IAEA CRP on Testing and Improving the International Reactor Dosimetry and Fusion File (IRDFF),
http://www-nds.iaea.org/IRDFFtest/.
- [Simakov2017] S. Simakov, et al., “Proposals for new measurements for IRDFF community and HPRL”, September 2017.
- [Pronyaev2013] V.G. Pronyaev, A.D. Carlson and R. Capote Noy, “Toward a New Evaluation of Neutron Standards”, IAEA Technical Meeting, 8-12 July 2013, INDC(NDS)-0641.
Review comment:
Entry Status:
Work in progress (as of SG-C review of May 2018)
Main references:
Please report any missing information to hprlinfo@oecd-nea.org
Theory/Evaluation
Additional file attached:Simakov2017.pdf
Additional file attached:Cf252U235_HighThreshold.pdf
Request ID | 68 |
Type of the request | Special Purpose Quantity |
Target | Reaction and process | Incident Energy | Secondary energy or angle | Target uncertainty | Covariance |
24-CR-52 | (n,2n) SIG,SPA | 252Cf(sf)-235U(n,f) | | 2-5 | Y |
Field | Subfield | Date Request created | Date Request accepted | Ongoing action |
Dosimetry | D-T fusion | 06-OCT-17 | 06-OCT-17 | |
Requester: Dr Stanislav SIMAKOV at KARLSRUHE, GER
Email: stanislav.simakov@partner.kit.edu
Project (context): IRDFF project
Impact:
The International Reactor Dosimetry and Fusion File (IRDFF) aims at providing evaluated neutron dosimetry reactions validated for all applications related to fission reactors and fusion technology development [IAEA2017].
Accuracy:
2%-5%
Justification document:
Accurate cross sections as well as spectrum-averaged cross sections (SACS) in relevant and well-characterized neutron fields are essential for improvement and validation of the evaluated data [Simakov2017].
Following a recommendation from the IAEA Data Development Project on Neutron Standards [Pronyaev2013], the IRDFF project supports SACS measurements of high-threshold (above 10 MeV) dosimetry cross-sections in well-characterized 252Cf(sf) and 235U(nth,f) neutron fields in order to improve the cross sections and/or the high-energy part of the prompt fission neutron spectra.
Comment from requester:
Measurements of the spectrum-averaged cross section are missing for validation purposes and for improvement of the cross section and prompt fission neutron spectrum above 10 MeV. See Cf252U235_HighThreshold.pdf below.
References
- [IAEA2017] IAEA CRP on Testing and Improving the International Reactor Dosimetry and Fusion File (IRDFF),
http://www-nds.iaea.org/IRDFFtest/.
- [Simakov2017] S. Simakov, et al., “Proposals for new measurements for IRDFF community and HPRL”, September 2017.
- [Pronyaev2013] V.G. Pronyaev, A.D. Carlson and R. Capote Noy, “Toward a New Evaluation of Neutron Standards”, IAEA Technical Meeting, 8-12 July 2013, INDC(NDS)-0641.
Review comment:
Entry Status:
Work in progress (as of SG-C review of May 2018)
Main references:
Please report any missing information to hprlinfo@oecd-nea.org
Theory/Evaluation
Additional file attached:Simakov2017.pdf
Additional file attached:Cf252U235_HighThreshold.pdf
Request ID | 69 |
Type of the request | Special Purpose Quantity |
Target | Reaction and process | Incident Energy | Secondary energy or angle | Target uncertainty | Covariance |
11-NA-23 | (n,2n) SIG,SPA | 252Cf(sf)-235U(n,f) | | 2-5 | Y |
Field | Subfield | Date Request created | Date Request accepted | Ongoing action |
Dosimetry | D-T fusion | 06-OCT-17 | 06-OCT-17 | |
Requester: Dr Stanislav SIMAKOV at KARLSRUHE, GER
Email: stanislav.simakov@partner.kit.edu
Project (context): IRDFF project
Impact:
The International Reactor Dosimetry and Fusion File (IRDFF) aims at providing evaluated neutron dosimetry reactions validated for all applications related to fission reactors and fusion technology development [IAEA2017].
Accuracy:
2%-5%
Justification document:
Accurate cross sections as well as spectrum-averaged cross sections (SACS) in relevant and well-characterized neutron fields are essential for improvement and validation of the evaluated data [Simakov2017].
Following a recommendation from the IAEA Data Development Project on Neutron Standards [Pronyaev2013], the IRDFF project supports SACS measurements of high-threshold (above 10 MeV) dosimetry cross-sections in well-characterized 252Cf(sf) and 235U(nth,f) neutron fields in order to improve the cross sections and/or the high-energy part of the prompt fission neutron spectra.
Comment from requester:
Measurements of the spectrum-averaged cross section are missing for validation purposes and for improvement of the cross section and prompt fission neutron spectrum above 10 MeV. See Cf252U235_HighThreshold.pdf below.
References
- [IAEA2017] IAEA CRP on Testing and Improving the International Reactor Dosimetry and Fusion File (IRDFF),
http://www-nds.iaea.org/IRDFFtest/.
- [Simakov2017] S. Simakov, et al., “Proposals for new measurements for IRDFF community and HPRL”, September 2017.
- [Pronyaev2013] V.G. Pronyaev, A.D. Carlson and R. Capote Noy, “Toward a New Evaluation of Neutron Standards”, IAEA Technical Meeting, 8-12 July 2013, INDC(NDS)-0641.
Review comment:
Entry Status:
Work in progress (as of SG-C review of May 2018)
Main references:
Please report any missing information to hprlinfo@oecd-nea.org
Experiments
- M. Schulc, M. Kostal, et al., Validation of differential cross sections by means of 252Cf spectral averaged cross sections, Applied Radiation and Isotopes 132 (2018) 29
- M. Schulc, et al., Investigation of 127I(n,2n)126I and 23Na(n,2n)22Na reactions using 252Cf neutron source, ASME J of Nuclear Rad Sci. 5 (2019) 030918
- M. Kostal, et al., A reference neutron field for measurement of spectrum averaged cross sections, Annals of Nuclear Energy 140 (2020) 107119
Theory/Evaluation
Additional file attached:Simakov2017.pdf
Additional file attached:Cf252U235_HighThreshold.pdf
Request ID | 70 |
Type of the request | Special Purpose Quantity |
Target | Reaction and process | Incident Energy | Secondary energy or angle | Target uncertainty | Covariance |
13-AL-27 | (n,2n) SIG,SPA | 252Cf(sf)-235U(n,f) | | 2-5 | Y |
Field | Subfield | Date Request created | Date Request accepted | Ongoing action |
Dosimetry | D-T fusion | 06-OCT-17 | 06-OCT-17 | |
Requester: Dr Stanislav SIMAKOV at KARLSRUHE, GER
Email: stanislav.simakov@partner.kit.edu
Project (context): IRDFF project
Impact:
The International Reactor Dosimetry and Fusion File (IRDFF) aims at providing evaluated neutron dosimetry reactions validated for all applications related to fission reactors and fusion technology development [IAEA2017].
Accuracy:
2%-5%
Justification document:
Accurate cross sections as well as spectrum-averaged cross sections (SACS) in relevant and well-characterized neutron fields are essential for improvement and validation of the evaluated data [Simakov2017].
Following a recommendation from the IAEA Data Development Project on Neutron Standards [Pronyaev2013], the IRDFF project supports SACS measurements of high-threshold (above 10 MeV) dosimetry cross-sections in well-characterized 252Cf(sf) and 235U(nth,f) neutron fields in order to improve the cross sections and/or the high-energy part of the prompt fission neutron spectra.
Comment from requester:
Measurements of the spectrum-averaged cross section are missing for validation purposes and for improvement of the cross section and prompt fission neutron spectrum above 10 MeV. See Cf252U235_HighThreshold.pdf below.
References
- [IAEA2017] IAEA CRP on Testing and Improving the International Reactor Dosimetry and Fusion File (IRDFF),
http://www-nds.iaea.org/IRDFFtest/.
- [Simakov2017] S. Simakov, et al., “Proposals for new measurements for IRDFF community and HPRL”, September 2017.
- [Pronyaev2013] V.G. Pronyaev, A.D. Carlson and R. Capote Noy, “Toward a New Evaluation of Neutron Standards”, IAEA Technical Meeting, 8-12 July 2013, INDC(NDS)-0641.
Review comment:
Entry Status:
Work in progress (as of SG-C review of May 2018)
Main references:
Please report any missing information to hprlinfo@oecd-nea.org
Theory/Evaluation
Additional file attached:Simakov2017.pdf
Additional file attached:Cf252U235_HighThreshold.pdf
Request ID | 71 |
Type of the request | Special Purpose Quantity |
Target | Reaction and process | Incident Energy | Secondary energy or angle | Target uncertainty | Covariance |
22-TI-46 | (n,2n) SIG,SPA | 252Cf(sf)-235U(n,f) | | 2-5 | Y |
Field | Subfield | Date Request created | Date Request accepted | Ongoing action |
Dosimetry | D-T fusion | 06-OCT-17 | 06-OCT-17 | |
Requester: Dr Stanislav SIMAKOV at KARLSRUHE, GER
Email: stanislav.simakov@partner.kit.edu
Project (context): IRDFF project
Impact:
The International Reactor Dosimetry and Fusion File (IRDFF) aims at providing evaluated neutron dosimetry reactions validated for all applications related to fission reactors and fusion technology development [IAEA2017].
Accuracy:
2%-5%
Justification document:
Accurate cross sections as well as spectrum-averaged cross sections (SACS) in relevant and well-characterized neutron fields are essential for improvement and validation of the evaluated data [Simakov2017].
Following a recommendation from the IAEA Data Development Project on Neutron Standards [Pronyaev2013], the IRDFF project supports SACS measurements of high-threshold (above 10 MeV) dosimetry cross-sections in well-characterized 252Cf(sf) and 235U(nth,f) neutron fields in order to improve the cross sections and/or the high-energy part of the prompt fission neutron spectra.
Comment from requester:
Measurements of the spectrum-averaged cross section are requested for validation purposes in 235U(n,f) neutron fields, for solving C/E discrepancy in 252Cf(sf) fields, and for improvement of the cross section and prompt fission neutron spectrum above 10 MeV. See CE_Cf252U235_and_HighThreshold.pdf below.
References
- [IAEA2017] IAEA CRP on Testing and Improving the International Reactor Dosimetry and Fusion File (IRDFF),
http://www-nds.iaea.org/IRDFFtest/.
- [Simakov2017] S. Simakov, et al., “Proposals for new measurements for IRDFF community and HPRL”, September 2017.
- [Pronyaev2013] V.G. Pronyaev, A.D. Carlson and R. Capote Noy, “Toward a New Evaluation of Neutron Standards”, IAEA Technical Meeting, 8-12 July 2013, INDC(NDS)-0641.
Review comment:
Entry Status:
Work in progress (as of SG-C review of May 2018)
Main references:
Please report any missing information to hprlinfo@oecd-nea.org
Theory/Evaluation
Additional file attached:Simakov2017.pdf
Additional file attached:CE_Cf252U235_and_HighThreshold.pdf
Request ID | 72 |
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,SPA | 252Cf(sf)-235U(n,f) | | 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
Additional file attached:Simakov2017.pdf
Additional file attached:Sn117(n,n)Sn117m.pdf
Request ID | 73 |
Type of the request | Special Purpose Quantity |
Target | Reaction and process | Incident Energy | Secondary energy or angle | Target uncertainty | Covariance |
22-TI-47 | (n,np) SIG,SPA | 252Cf(sf)-235U(n,f) | | 5-10 | Y |
Field | Subfield | Date Request created | Date Request accepted | Ongoing action |
Dosimetry | D-T fusion, high-energy | 06-OCT-17 | 06-OCT-17 | |
Requester: Dr Stanislav SIMAKOV at KARLSRUHE, GER
Email: stanislav.simakov@partner.kit.edu
Project (context): IRDFF project
Impact:
The International Reactor Dosimetry and Fusion File (IRDFF) aims at providing evaluated neutron dosimetry reactions validated for all applications related to fission reactors and fusion technology development [IAEA2017].
Accuracy:
5%-10%
Justification document:
Accurate cross sections as well as spectrum-averaged cross sections (SACS) in relevant and well-characterized neutron fields are essential for improvement and validation of the evaluated data [Simakov2017].
Following a recommendation from the IAEA Data Development Project on Neutron Standards [Pronyaev2013], the IRDFF project supports SACS measurements of high-threshold (above 10 MeV) dosimetry cross-sections in well-characterized 252Cf(sf) and 235U(nth,f) neutron fields in order to improve the cross sections and/or the high-energy part of the prompt fission neutron spectra.
Comment from requester:
Measurements of the spectrum-averaged cross section are missing for validation purposes and for improvement of the cross section and prompt fission neutron spectrum above 10 MeV.
References
- [IAEA2017] IAEA CRP on Testing and Improving the International Reactor Dosimetry and Fusion File (IRDFF),
http://www-nds.iaea.org/IRDFFtest/.
- [Simakov2017] S. Simakov, et al., “Proposals for new measurements for IRDFF community and HPRL”, September 2017.
- [Pronyaev2013] V.G. Pronyaev, A.D. Carlson and R. Capote Noy, “Toward a New Evaluation of Neutron Standards”, IAEA Technical Meeting, 8-12 July 2013, INDC(NDS)-0641.
Review comment:
Entry Status:
Work in progress (as of SG-C review of May 2018)
Main references:
Please report any missing information to hprlinfo@oecd-nea.org
Theory/Evaluation
Additional file attached:Simakov2017.pdf
Additional file attached:
Request ID | 74 |
Type of the request | Special Purpose Quantity |
Target | Reaction and process | Incident Energy | Secondary energy or angle | Target uncertainty | Covariance |
22-TI-48 | (n,np) SIG,SPA | 252Cf(sf)-235U(n,f) | | 5-10 | Y |
Field | Subfield | Date Request created | Date Request accepted | Ongoing action |
Dosimetry | D-T fusion, high-energy | 06-OCT-17 | 06-OCT-17 | |
Requester: Dr Stanislav SIMAKOV at KARLSRUHE, GER
Email: stanislav.simakov@partner.kit.edu
Project (context): IRDFF project
Impact:
The International Reactor Dosimetry and Fusion File (IRDFF) aims at providing evaluated neutron dosimetry reactions validated for all applications related to fission reactors and fusion technology development [IAEA2017].
Accuracy:
5%-10%
Justification document:
Accurate cross sections as well as spectrum-averaged cross sections (SACS) in relevant and well-characterized neutron fields are essential for improvement and validation of the evaluated data [Simakov2017].
Following a recommendation from the IAEA Data Development Project on Neutron Standards [Pronyaev2013], the IRDFF project supports SACS measurements of high-threshold (above 10 MeV) dosimetry cross-sections in well-characterized 252Cf(sf) and 235U(nth,f) neutron fields in order to improve the cross sections and/or the high-energy part of the prompt fission neutron spectra.
Comment from requester:
Measurements of the spectrum-averaged cross section are missing for validation purposes and for improvement of the cross section and prompt fission neutron spectrum above 10 MeV.
References
- [IAEA2017] IAEA CRP on Testing and Improving the International Reactor Dosimetry and Fusion File (IRDFF),
http://www-nds.iaea.org/IRDFFtest/.
- [Simakov2017] S. Simakov, et al., “Proposals for new measurements for IRDFF community and HPRL”, September 2017.
- [Pronyaev2013] V.G. Pronyaev, A.D. Carlson and R. Capote Noy, “Toward a New Evaluation of Neutron Standards”, IAEA Technical Meeting, 8-12 July 2013, INDC(NDS)-0641.
Review comment:
Entry Status:
Work in progress (as of SG-C review of May 2018)
Main references:
Please report any missing information to hprlinfo@oecd-nea.org
Theory/Evaluation
Additional file attached:Simakov2017.pdf
Additional file attached:
Request ID | 75 |
Type of the request | Special Purpose Quantity |
Target | Reaction and process | Incident Energy | Secondary energy or angle | Target uncertainty | Covariance |
22-TI-49 | (n,np) SIG,SPA | 252Cf(sf)-235U(n,f) | | 5-10 | Y |
Field | Subfield | Date Request created | Date Request accepted | Ongoing action |
Dosimetry | D-T fusion, high-energy | 06-OCT-17 | 06-OCT-17 | |
Requester: Dr Stanislav SIMAKOV at KARLSRUHE, GER
Email: stanislav.simakov@partner.kit.edu
Project (context): IRDFF project
Impact:
The International Reactor Dosimetry and Fusion File (IRDFF) aims at providing evaluated neutron dosimetry reactions validated for all applications related to fission reactors and fusion technology development [IAEA2017].
Accuracy:
5%-10%
Justification document:
Accurate cross sections as well as spectrum-averaged cross sections (SACS) in relevant and well-characterized neutron fields are essential for improvement and validation of the evaluated data [Simakov2017].
Following a recommendation from the IAEA Data Development Project on Neutron Standards [Pronyaev2013], the IRDFF project supports SACS measurements of high-threshold (above 10 MeV) dosimetry cross-sections in well-characterized 252Cf(sf) and 235U(nth,f) neutron fields in order to improve the cross sections and/or the high-energy part of the prompt fission neutron spectra.
Comment from requester:
Measurements of the spectrum-averaged cross section are missing for validation purposes and for improvement of the cross section and prompt fission neutron spectrum above 10 MeV.
References
- [IAEA2017] IAEA CRP on Testing and Improving the International Reactor Dosimetry and Fusion File (IRDFF),
http://www-nds.iaea.org/IRDFFtest/.
- [Simakov2017] S. Simakov, et al., “Proposals for new measurements for IRDFF community and HPRL”, September 2017.
- [Pronyaev2013] V.G. Pronyaev, A.D. Carlson and R. Capote Noy, “Toward a New Evaluation of Neutron Standards”, IAEA Technical Meeting, 8-12 July 2013, INDC(NDS)-0641.
Review comment:
Entry Status:
Work in progress (as of SG-C review of May 2018)
Main references:
Please report any missing information to hprlinfo@oecd-nea.org
Theory/Evaluation
Additional file attached:Simakov2017.pdf
Additional file attached:
Request ID | 76 |
Type of the request | Special Purpose Quantity |
Target | Reaction and process | Incident Energy | Secondary energy or angle | Target uncertainty | Covariance |
26-FE-54 | (n,2n) SIG,SPA | 252Cf(sf)-235U(n,f) | | 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 KARLSRUHE, GER
Email: stanislav.simakov@partner.kit.edu
Project (context): IRDFF project
Impact:
The International Reactor Dosimetry and Fusion File (IRDFF) aims at providing evaluated neutron dosimetry reactions validated for all applications related to fission reactors and fusion technology development [IAEA2017].
Accuracy:
5%-10%
Justification document:
Accurate cross sections as well as spectrum-averaged cross sections (SACS) in relevant and well-characterized neutron fields are essential for improvement and validation of the evaluated data [Simakov2017].
Following a recommendation from the IAEA Data Development Project on Neutron Standards [Pronyaev2013], the IRDFF project supports SACS measurements of high-threshold (above 10 MeV) dosimetry cross-sections in well-characterized 252Cf(sf) and 235U(nth,f) neutron fields in order to improve the cross sections and/or the high-energy part of the prompt fission neutron spectra.
Comment from requester:
Measurements of the spectrum-averaged cross section are missing for validation purposes and for improvement of the cross section and prompt fission neutron spectrum above 10 MeV. See Cf252U235_HighThreshold.pdf below.
References
- [IAEA2017] IAEA CRP on Testing and Improving the International Reactor Dosimetry and Fusion File (IRDFF),
http://www-nds.iaea.org/IRDFFtest/.
- [Simakov2017] S. Simakov, et al., “Proposals for new measurements for IRDFF community and HPRL”, September 2017.
- [Pronyaev2013] V.G. Pronyaev, A.D. Carlson and R. Capote Noy, “Toward a New Evaluation of Neutron Standards”, IAEA Technical Meeting, 8-12 July 2013, INDC(NDS)-0641.
Review comment:
Entry Status:
Work in progress (as of SG-C review of May 2018)
Main references:
Please report any missing information to hprlinfo@oecd-nea.org
Theory/Evaluation
Additional file attached:Simakov2017.pdf
Additional file attached:Cf252U235_HighThreshold.pdf
Request ID | 77 |
Type of the request | Special Purpose Quantity |
Target | Reaction and process | Incident Energy | Secondary energy or angle | Target uncertainty | Covariance |
69-TM-169 | (n,3n) SIG,SPA | 252Cf(sf)-235U(n,f) | | 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 KARLSRUHE, GER
Email: stanislav.simakov@partner.kit.edu
Project (context): IRDFF project
Impact:
The International Reactor Dosimetry and Fusion File (IRDFF) aims at providing evaluated neutron dosimetry reactions validated for all applications related to fission reactors and fusion technology development [IAEA2017].
Accuracy:
5%-10%
Justification document:
Accurate cross sections as well as spectrum-averaged cross sections (SACS) in relevant and well-characterized neutron fields are essential for improvement and validation of the evaluated data [Simakov2017].
Following a recommendation from the IAEA Data Development Project on Neutron Standards [Pronyaev2013], the IRDFF project supports SACS measurements of high-threshold (above 10 MeV) dosimetry cross-sections in well-characterized 252Cf(sf) and 235U(nth,f) neutron fields in order to improve the cross sections and/or the high-energy part of the prompt fission neutron spectra.
Comment from requester:
Measurements of the spectrum-averaged cross section are missing for validation purposes and for improvement of the cross section and prompt fission neutron spectrum above 10 MeV. See Cf252U235_HighThreshold.pdf below.
References
- [IAEA2017] IAEA CRP on Testing and Improving the International Reactor Dosimetry and Fusion File (IRDFF),
http://www-nds.iaea.org/IRDFFtest/.
- [Simakov2017] S. Simakov, et al., “Proposals for new measurements for IRDFF community and HPRL”, September 2017.
- [Pronyaev2013] V.G. Pronyaev, A.D. Carlson and R. Capote Noy, “Toward a New Evaluation of Neutron Standards”, IAEA Technical Meeting, 8-12 July 2013, INDC(NDS)-0641.
Review comment:
Entry Status:
Work in progress (as of SG-C review of May 2018)
Main references:
Please report any missing information to hprlinfo@oecd-nea.org
Theory/Evaluation
Additional file attached:Simakov2017.pdf
Additional file attached:Cf252U235_HighThreshold.pdf
Request ID | 78 |
Type of the request | Special Purpose Quantity |
Target | Reaction and process | Incident Energy | Secondary energy or angle | Target uncertainty | Covariance |
83-BI-209 | (n,3n) SIG,SPA | 252Cf(sf)-235U(n,f) | | 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 KARLSRUHE, GER
Email: stanislav.simakov@partner.kit.edu
Project (context): IRDFF project
Impact:
The International Reactor Dosimetry and Fusion File (IRDFF) aims at providing evaluated neutron dosimetry reactions validated for all applications related to fission reactors and fusion technology development [IAEA2017].
Accuracy:
5%-10%
Justification document:
Accurate cross sections as well as spectrum-averaged cross sections (SACS) in relevant and well-characterized neutron fields are essential for improvement and validation of the evaluated data [Simakov2017].
Following a recommendation from the IAEA Data Development Project on Neutron Standards [Pronyaev2013], the IRDFF project supports SACS measurements of high-threshold (above 10 MeV) dosimetry cross-sections in well-characterized 252Cf(sf) and 235U(nth,f) neutron fields in order to improve the cross sections and/or the high-energy part of the prompt fission neutron spectra.
Comment from requester:
Measurements of the spectrum-averaged cross section are missing for validation purposes and for improvement of the cross section and prompt fission neutron spectrum above 10 MeV. See Cf252U235_HighThreshold.pdf below.
References
- [IAEA2017] IAEA CRP on Testing and Improving the International Reactor Dosimetry and Fusion File (IRDFF),
http://www-nds.iaea.org/IRDFFtest/.
- [Simakov2017] S. Simakov, et al., “Proposals for new measurements for IRDFF community and HPRL”, September 2017.
- [Pronyaev2013] V.G. Pronyaev, A.D. Carlson and R. Capote Noy, “Toward a New Evaluation of Neutron Standards”, IAEA Technical Meeting, 8-12 July 2013, INDC(NDS)-0641.
Review comment:
Entry Status:
Work in progress (as of SG-C review of May 2018)
Main references:
Please report any missing information to hprlinfo@oecd-nea.org
Experiments
Theory/Evaluation
Additional file attached:Simakov2017.pdf
Additional file attached:Cf252U235_HighThreshold.pdf
Request ID | 79 |
Type of the request | Special Purpose Quantity |
Target | Reaction and process | Incident Energy | Secondary energy or angle | Target uncertainty | Covariance |
27-CO-59 | (n,3n) SIG,SPA | 252Cf(sf)-235U(n,f) | | 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 KARLSRUHE, GER
Email: stanislav.simakov@partner.kit.edu
Project (context): IRDFF project
Impact:
The International Reactor Dosimetry and Fusion File (IRDFF) aims at providing evaluated neutron dosimetry reactions validated for all applications related to fission reactors and fusion technology development [IAEA2017].
Accuracy:
5%-10%
Justification document:
Accurate cross sections as well as spectrum-averaged cross sections (SACS) in relevant and well-characterized neutron fields are essential for improvement and validation of the evaluated data [Simakov2017].
Following a recommendation from the IAEA Data Development Project on Neutron Standards [Pronyaev2013], the IRDFF project supports SACS measurements of high-threshold (above 10 MeV) dosimetry cross-sections in well-characterized 252Cf(sf) and 235U(nth,f) neutron fields in order to improve the cross sections and/or the high-energy part of the prompt fission neutron spectra.
Comment from requester:
Measurements of the spectrum-averaged cross section are missing for validation purposes and for improvement of the cross section and prompt fission neutron spectrum above 10 MeV. See Cf252U235_HighThreshold.pdf below.
References
- [IAEA2017] IAEA CRP on Testing and Improving the International Reactor Dosimetry and Fusion File (IRDFF),
http://www-nds.iaea.org/IRDFFtest/.
- [Simakov2017] S. Simakov, et al., “Proposals for new measurements for IRDFF community and HPRL”, September 2017.
- [Pronyaev2013] V.G. Pronyaev, A.D. Carlson and R. Capote Noy, “Toward a New Evaluation of Neutron Standards”, IAEA Technical Meeting, 8-12 July 2013, INDC(NDS)-0641.
Review comment:
Entry Status:
Work in progress (as of SG-C review of May 2018)
Main references:
Please report any missing information to hprlinfo@oecd-nea.org
Theory/Evaluation
Additional file attached:Simakov2017.pdf
Additional file attached:Cf252U235_HighThreshold.pdf
Request 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 | 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 KARLSRUHE, GER
Email: stanislav.simakov@partner.kit.edu
Project (context): IRDFF project
Impact:
The International Reactor Dosimetry and Fusion File (IRDFF) aims at providing evaluated neutron dosimetry reactions validated for all applications related to fission reactors and fusion technology development [IAEA2017].
Accuracy:
5%-10%
Justification document:
Accurate cross sections as well as spectrum-averaged cross sections (SACS) in relevant and well-characterized neutron fields are essential for improvement and validation of the evaluated data [Simakov2017].
Comment from requester:
The IRDFF project strives to evaluate, and eventually add to the library, high-threshold reactions with cross section plateaus located between 15/20 MeV and 100/150 MeV to meet the requirements of the accelerator-driven high-energy neutron sources. Note that it is important to know the cross section tail up to 100/150 MeV in order to allow the deconvolution of high-energy quasi-monoenergetic neutron source spectra.
References
- [IAEA2017] IAEA CRP on Testing and Improving the International Reactor Dosimetry and Fusion File (IRDFF),
http://www-nds.iaea.org/IRDFFtest/.
- [Simakov2017] S. Simakov, et al., “Proposals for new measurements for IRDFF community and HPRL”, September 2017.
Review comment:
Entry Status:
Work in progress (as of SG-C review of May 2018)
Main references:
Please report any missing information to hprlinfo@oecd-nea.org
Experiments
Theory/Evaluation
- 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 | 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 KARLSRUHE, GER
Email: stanislav.simakov@partner.kit.edu
Project (context): IRDFF project
Impact:
The International Reactor Dosimetry and Fusion File (IRDFF) aims at providing evaluated neutron dosimetry reactions validated for all applications related to fission reactors and fusion technology development [IAEA2017].
Accuracy:
5%-10%
Justification document:
Accurate cross sections as well as spectrum-averaged cross sections (SACS) in relevant and well-characterized neutron fields are essential for improvement and validation of the evaluated data [Simakov2017].
Comment from requester:
The IRDFF project strives to evaluate, and eventually add to the library, high-threshold reactions with cross section plateaus located between 15/20 MeV and 100/150 MeV to meet the requirements of the accelerator-driven high-energy neutron sources. Note that it is important to know the cross section tail up to 100/150 MeV in order to allow the deconvolution of high-energy quasi-monoenergetic neutron source spectra.
References
- [IAEA2017] IAEA CRP on Testing and Improving the International Reactor Dosimetry and Fusion File (IRDFF),
http://www-nds.iaea.org/IRDFFtest/.
- [Simakov2017] S. Simakov, et al., “Proposals for new measurements for IRDFF community and HPRL”, September 2017.
Review comment:
Entry Status:
Work in progress (as of SG-C review of May 2018)
Main references:
Please report any missing information to hprlinfo@oecd-nea.org
Additional file attached:Simakov2017.pdf
Additional file attached:Y89(n,xn).pdf
Request 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 KARLSRUHE, GER
Email: stanislav.simakov@partner.kit.edu
Project (context): IRDFF project
Impact:
The International Reactor Dosimetry and Fusion File (IRDFF) aims at providing evaluated neutron dosimetry reactions validated for all applications related to fission reactors and fusion technology development [IAEA2017].
Accuracy:
5%-10%
Justification document:
Accurate cross sections as well as spectrum-averaged cross sections (SACS) in relevant and well-characterized neutron fields are essential for improvement and validation of the evaluated data [Simakov2017].
Comment from requester:
The IRDFF project strives to evaluate, and eventually add to the library, high-threshold reactions with cross section plateaus located between 15/20 MeV and 100/150 MeV to meet the requirements of the accelerator-driven high-energy neutron sources. Note that it is important to know the cross section tail up to 100/150 MeV in order to allow the deconvolution of high-energy quasi-monoenergetic neutron source spectra.
References
- [IAEA2017] IAEA CRP on Testing and Improving the International Reactor Dosimetry and Fusion File (IRDFF),
http://www-nds.iaea.org/IRDFFtest/.
- [Simakov2017] S. Simakov, et al., “Proposals for new measurements for IRDFF community and HPRL”, September 2017.
Review comment:
Entry Status:
Work in progress (as of SG-C review of May 2018)
Main references:
Please report any missing information to hprlinfo@oecd-nea.org
Experiments
Theory/Evaluation
Additional file attached:Simakov2017.pdf
Additional file attached:Y89(n,xn).pdf
Request 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 KARLSRUHE, GER
Email: stanislav.simakov@partner.kit.edu
Project (context): IRDFF project
Impact:
The International Reactor Dosimetry and Fusion File (IRDFF) aims at providing evaluated neutron dosimetry reactions validated for all applications related to fission reactors and fusion technology development [IAEA2017].
Accuracy:
5%-10%
Justification document:
Accurate cross sections as well as spectrum-averaged cross sections (SACS) in relevant and well-characterized neutron fields are essential for improvement and validation of the evaluated data [Simakov2017].
Comment from requester:
The IRDFF project strives to evaluate, and eventually add to the library, high-threshold reactions with cross section plateaus located between 15/20 MeV and 100/150 MeV to meet the requirements of the accelerator-driven high-energy neutron sources. Note that it is important to know the cross section tail up to 100/150 MeV in order to allow the deconvolution of high-energy quasi-monoenergetic neutron source spectra.
References
- [IAEA2017] IAEA CRP on Testing and Improving the International Reactor Dosimetry and Fusion File (IRDFF),
http://www-nds.iaea.org/IRDFFtest/.
- [Simakov2017] S. Simakov, et al., “Proposals for new measurements for IRDFF community and HPRL”, September 2017.
Review comment:
Entry Status:
Work in progress (as of SG-C review of May 2018)
Main references:
Please report any missing information to hprlinfo@oecd-nea.org
Theory/Evaluation
Additional file attached:Simakov2017.pdf
Additional file attached:
Request 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 KARLSRUHE, GER
Email: stanislav.simakov@partner.kit.edu
Project (context): IRDFF project
Impact:
The International Reactor Dosimetry and Fusion File (IRDFF) aims at providing evaluated neutron dosimetry reactions validated for all applications related to fission reactors and fusion technology development [IAEA2017].
Accuracy:
5%-10%
Justification document:
Accurate cross sections as well as spectrum-averaged cross sections (SACS) in relevant and well-characterized neutron fields are essential for improvement and validation of the evaluated data [Simakov2017].
Comment from requester:
The IRDFF project strives to evaluate, and eventually add to the library, high-threshold reactions with cross section plateaus located between 15/20 MeV and 100/150 MeV to meet the requirements of the accelerator-driven high-energy neutron sources. Note that it is important to know the cross section tail up to 100/150 MeV in order to allow the deconvolution of high-energy quasi-monoenergetic neutron source spectra.
References
- [IAEA2017] IAEA CRP on Testing and Improving the International Reactor Dosimetry and Fusion File (IRDFF),
http://www-nds.iaea.org/IRDFFtest/.
- [Simakov2017] S. Simakov, et al., “Proposals for new measurements for IRDFF community and HPRL”, September 2017.
Review comment:
Entry Status:
Work in progress (as of SG-C review of May 2018)
Main references:
Please report any missing information to hprlinfo@oecd-nea.org
Theory/Evaluation
Additional file attached:Simakov2017.pdf
Additional file attached:
Request 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 KARLSRUHE, GER
Email: stanislav.simakov@partner.kit.edu
Project (context): IRDFF project
Impact:
The International Reactor Dosimetry and Fusion File (IRDFF) aims at providing evaluated neutron dosimetry reactions validated for all applications related to fission reactors and fusion technology development [IAEA2017].
Accuracy:
5%-10%
Justification document:
Accurate cross sections as well as spectrum-averaged cross sections (SACS) in relevant and well-characterized neutron fields are essential for improvement and validation of the evaluated data [Simakov2017].
Comment from requester:
The IRDFF project strives to evaluate, and eventually add to the library, high-threshold reactions with cross section plateaus located between 15/20 MeV and 100/150 MeV to meet the requirements of the accelerator-driven high-energy neutron sources. Note that it is important to know the cross section tail up to 100/150 MeV in order to allow the deconvolution of high-energy quasi-monoenergetic neutron source spectra.
References
- [IAEA2017] IAEA CRP on Testing and Improving the International Reactor Dosimetry and Fusion File (IRDFF),
http://www-nds.iaea.org/IRDFFtest/.
- [Simakov2017] S. Simakov, et al., “Proposals for new measurements for IRDFF community and HPRL”, September 2017.
Review comment:
Entry Status:
Work in progress (as of SG-C review of May 2018)
Main references:
Please report any missing information to hprlinfo@oecd-nea.org
Theory/Evaluation
Additional file attached:Simakov2017.pdf
Additional file attached:
Request 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 KARLSRUHE, GER
Email: stanislav.simakov@partner.kit.edu
Project (context): IRDFF project
Impact:
The International Reactor Dosimetry and Fusion File (IRDFF) aims at providing evaluated neutron dosimetry reactions validated for all applications related to fission reactors and fusion technology development [IAEA2017].
Accuracy:
5%-10%
Justification document:
Accurate cross sections as well as spectrum-averaged cross sections (SACS) in relevant and well-characterized neutron fields are essential for improvement and validation of the evaluated data [Simakov2017].
Comment from requester:
The IRDFF project strives to evaluate, and eventually add to the library, high-threshold reactions with cross section plateaus located between 15/20 MeV and 100/150 MeV to meet the requirements of the accelerator-driven high-energy neutron sources. Note that it is important to know the cross section tail up to 100/150 MeV in order to allow the deconvolution of high-energy quasi-monoenergetic neutron source spectra.
References
- [IAEA2017] IAEA CRP on Testing and Improving the International Reactor Dosimetry and Fusion File (IRDFF),
http://www-nds.iaea.org/IRDFFtest/.
- [Simakov2017] S. Simakov, et al., “Proposals for new measurements for IRDFF community and HPRL”, September 2017.
Review comment:
Entry Status:
Work in progress (as of SG-C review of May 2018)
Main references:
Please report any missing information to hprlinfo@oecd-nea.org
Additional file attached:Simakov2017.pdf
Additional file attached:Lu(n,xn).pdf
Request 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 KARLSRUHE, GER
Email: stanislav.simakov@partner.kit.edu
Project (context): IRDFF project
Impact:
The International Reactor Dosimetry and Fusion File (IRDFF) aims at providing evaluated neutron dosimetry reactions validated for all applications related to fission reactors and fusion technology development [IAEA2017].
Accuracy:
5%-10%
Justification document:
Accurate cross sections as well as spectrum-averaged cross sections (SACS) in relevant and well-characterized neutron fields are essential for improvement and validation of the evaluated data [Simakov2017].
Comment from requester:
The IRDFF project strives to evaluate, and eventually add to the library, high-threshold reactions with cross section plateaus located between 15/20 MeV and 100/150 MeV to meet the requirements of the accelerator-driven high-energy neutron sources. Note that it is important to know the cross section tail up to 100/150 MeV in order to allow the deconvolution of high-energy quasi-monoenergetic neutron source spectra.
The present request concerns the following reactions:
Nb-93(n,2n)Nb-92m
Nb-93(n,3n)Nb-91m
Nb-93(n,4n)Nb-90
References
- [IAEA2017] IAEA CRP on Testing and Improving the International Reactor Dosimetry and Fusion File (IRDFF),
http://www-nds.iaea.org/IRDFFtest/.
- [Simakov2017] S. Simakov, et al., “Proposals for new measurements for IRDFF community and HPRL”, September 2017.
Review comment:
Entry Status:
Work in progress (as of SG-C review of May 2018)
Main references:
Please report any missing information to hprlinfo@oecd-nea.org
Experiments
- M. Majerle, P. Bem, et al., Au, Bi, Co and Nb cross-section measured by quasimonoenergetic neutrons from p+7Li reaction in the energy range of 18-36 MeV, Nuclear Physics A 953 (2016) 139
Theory/Evaluation
Additional file attached:Simakov2017.pdf
Additional file attached:Nb(n,xn).pdf
Request ID | 89 |
Type of the request | Special Purpose Quantity |
Target | Reaction and process | Incident Energy | Secondary energy or angle | Target uncertainty | Covariance |
29-CU-63 | (n,2n) SIG | 20 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 KARLSRUHE, GER
Email: stanislav.simakov@partner.kit.edu
Project (context): IRDFF project
Impact:
The International Reactor Dosimetry and Fusion File (IRDFF) aims at providing evaluated neutron dosimetry reactions validated for all applications related to fission reactors and fusion technology development [IAEA2017].
Accuracy:
5%-10%
Justification document:
Accurate cross sections as well as spectrum-averaged cross sections (SACS) in relevant and well-characterized neutron fields are essential for improvement and validation of the evaluated data [Simakov2017].
Comment from requester:
The IRDFF project strives to evaluate, and eventually add to the library, high-threshold reactions with cross section plateaus located between 15/20 MeV and 100/150 MeV to meet the requirements of the accelerator-driven high-energy neutron sources. Note that it is important to know the cross section tail up to 100/150 MeV in order to allow the deconvolution of high-energy quasi-monoenergetic neutron source spectra.
References
- [IAEA2017] IAEA CRP on Testing and Improving the International Reactor Dosimetry and Fusion File (IRDFF),
http://www-nds.iaea.org/IRDFFtest/.
- [Simakov2017] S. Simakov, et al., “Proposals for new measurements for IRDFF community and HPRL”, September 2017.
Review comment:
Entry Status:
Work in progress (as of SG-C review of May 2018)
Main references:
Please report any missing information to hprlinfo@oecd-nea.org
Theory/Evaluation
Additional file attached:Simakov2017.pdf
Additional file attached:
Request ID | 90 |
Type of the request | Special Purpose Quantity |
Target | Reaction and process | Incident Energy | Secondary energy or angle | Target uncertainty | Covariance |
26-FE-54 | (n,2n) 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 KARLSRUHE, GER
Email: stanislav.simakov@partner.kit.edu
Project (context): IRDFF project
Impact:
The International Reactor Dosimetry and Fusion File (IRDFF) aims at providing evaluated neutron dosimetry reactions validated for all applications related to fission reactors and fusion technology development [IAEA2017].
Accuracy:
5%-10%
Justification document:
Accurate cross sections as well as spectrum-averaged cross sections (SACS) in relevant and well-characterized neutron fields are essential for improvement and validation of the evaluated data [Simakov2017].
Comment from requester:
The IRDFF project strives to evaluate, and eventually add to the library, high-threshold reactions with cross section plateaus located between 15/20 MeV and 100/150 MeV to meet the requirements of the accelerator-driven high-energy neutron sources. Note that it is important to know the cross section tail up to 100/150 MeV in order to allow the deconvolution of high-energy quasi-monoenergetic neutron source spectra.
References
- [IAEA2017] IAEA CRP on Testing and Improving the International Reactor Dosimetry and Fusion File (IRDFF),
http://www-nds.iaea.org/IRDFFtest/.
- [Simakov2017] S. Simakov, et al., “Proposals for new measurements for IRDFF community and HPRL”, September 2017.
Review comment:
Entry Status:
Work in progress (as of SG-C review of May 2018)
Main references:
Please report any missing information to hprlinfo@oecd-nea.org
Experiments
Theory/Evaluation
Additional file attached:Simakov2017.pdf
Additional file attached:Fe54n2n.pdf
Request 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 KARLSRUHE, GER
Email: stanislav.simakov@partner.kit.edu
Project (context): IRDFF project
Impact:
The International Reactor Dosimetry and Fusion File (IRDFF) aims at providing evaluated neutron dosimetry reactions validated for all applications related to fission reactors and fusion technology development [IAEA2017].
Accuracy:
5%-10%
Justification document:
Accurate cross sections as well as spectrum-averaged cross sections (SACS) in relevant and well-characterized neutron fields are essential for improvement and validation of the evaluated data [Simakov2017].
Comment from requester:
The IRDFF project strives to evaluate, and eventually add to the library, high-threshold reactions with cross section plateaus located between 15/20 MeV and 100/150 MeV to meet the requirements of the accelerator-driven high-energy neutron sources. Note that it is important to know the cross section tail up to 100/150 MeV in order to allow the deconvolution of high-energy quasi-monoenergetic neutron source spectra.
References
- [IAEA2017] IAEA CRP on Testing and Improving the International Reactor Dosimetry and Fusion File (IRDFF),
http://www-nds.iaea.org/IRDFFtest/.
- [Simakov2017] S. Simakov, et al., “Proposals for new measurements for IRDFF community and HPRL”, September 2017.
Review comment:
Entry Status:
Work in progress (as of SG-C review of May 2018)
Main references:
Please report any missing information to hprlinfo@oecd-nea.org
Experiments
- M. Majerle, P. Bem, et al., Au, Bi, Co and Nb cross-section measured by quasimonoenergetic neutrons from p+7Li reaction in the energy range of 18-36 MeV, Nuclear Physics A 953 (2016) 139
- 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(nth,f) prompt fission neutron spectrum, Applied Radiation and Isotopes 166 (2020) 109313
Additional file attached:Simakov2017.pdf
Additional file attached:Au(n,xn)_HighEnDos.pdf
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 KARLSRUHE, GER
Email: stanislav.simakov@partner.kit.edu
Project (context): IRDFF project
Impact:
The International Reactor Dosimetry and Fusion File (IRDFF) aims at providing evaluated neutron dosimetry reactions validated for all applications related to fission reactors and fusion technology development [IAEA2017].
Accuracy:
5%-10%
Justification document:
Accurate cross sections as well as spectrum-averaged cross sections (SACS) in relevant and well-characterized neutron fields are essential for improvement and validation of the evaluated data [Simakov2017].
Comment from requester:
The IRDFF project strives to evaluate, and eventually add to the library, high-threshold reactions with cross section plateaus located between 15/20 MeV and 100/150 MeV to meet the requirements of the accelerator-driven high-energy neutron sources. Note that it is important to know the cross section tail up to 100/150 MeV in order to allow the deconvolution of high-energy quasi-monoenergetic neutron source spectra.
References
- [IAEA2017] IAEA CRP on Testing and Improving the International Reactor Dosimetry and Fusion File (IRDFF),
http://www-nds.iaea.org/IRDFFtest/.
- [Simakov2017] S. Simakov, et al., “Proposals for new measurements for IRDFF community and HPRL”, September 2017.
Review comment:
Entry Status:
Work in progress (as of SG-C review of May 2018)
Main references:
Please report any missing information to hprlinfo@oecd-nea.org
Experiments
Theory/Evaluation
Additional file attached:Simakov2017.pdf
Additional file attached:Tm(n,xn).pdf
Request 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 KARLSRUHE, GER
Email: stanislav.simakov@partner.kit.edu
Project (context): IRDFF project
Impact:
The International Reactor Dosimetry and Fusion File (IRDFF) aims at providing evaluated neutron dosimetry reactions validated for all applications related to fission reactors and fusion technology development [IAEA2017].
Accuracy:
5%-10%
Justification document:
Accurate cross sections as well as spectrum-averaged cross sections (SACS) in relevant and well-characterized neutron fields are essential for improvement and validation of the evaluated data [Simakov2017].
Comment from requester:
The IRDFF project strives to evaluate, and eventually add to the library, high-threshold reactions with cross section plateaus located between 15/20 MeV and 100/150 MeV to meet the requirements of the accelerator-driven high-energy neutron sources. Note that it is important to know the cross section tail up to 100/150 MeV in order to allow the deconvolution of high-energy quasi-monoenergetic neutron source spectra.
References
- [IAEA2017] IAEA CRP on Testing and Improving the International Reactor Dosimetry and Fusion File (IRDFF),
http://www-nds.iaea.org/IRDFFtest/.
- [Simakov2017] S. Simakov, et al., “Proposals for new measurements for IRDFF community and HPRL”, September 2017.
Review comment:
Entry Status:
Work in progress (as of SG-C review of May 2018)
Main references:
Please report any missing information to hprlinfo@oecd-nea.org
Experiments
- M. Majerle, P. Bem, et al., Au, Bi, Co and Nb cross-section measured by quasimonoenergetic neutrons from p+7Li reaction in the energy range of 18-36 MeV, Nuclear Physics A 953 (2016) 139
- M. Majerle, et al., Experimental Validation of IRDFF Cross-Sections in Quasi-MonoEnergetic Neutron Fluxes in 20-35 MeV Energy Range, IAEA report INDC(NDS)-0789, May 2019
- M. Schulc, et al., Constraining high energy tail of 235U(nth,f) prompt fission neutron spectrum, Applied Radiation and Isotopes 166 (2020) 109313
Theory/Evaluation
Additional file attached:Simakov2017.pdf
Additional file attached:Bi(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 KARLSRUHE, GER
Email: stanislav.simakov@partner.kit.edu
Project (context): IRDFF project
Impact:
The International Reactor Dosimetry and Fusion File (IRDFF) aims at providing evaluated neutron dosimetry reactions validated for all applications related to fission reactors and fusion technology development [IAEA2017].
Accuracy:
5%-10%
Justification document:
Accurate cross sections as well as spectrum-averaged cross sections (SACS) in relevant and well-characterized neutron fields are essential for improvement and validation of the evaluated data [Simakov2017].
Comment from requester:
The IRDFF project strives to evaluate, and eventually add to the library, high-threshold reactions with cross section plateaus located between 15/20 MeV and 100/150 MeV to meet the requirements of the accelerator-driven high-energy neutron sources. Note that it is important to know the cross section tail up to 100/150 MeV in order to allow the deconvolution of high-energy quasi-monoenergetic neutron source spectra.
References
- [IAEA2017] IAEA CRP on Testing and Improving the International Reactor Dosimetry and Fusion File (IRDFF),
http://www-nds.iaea.org/IRDFFtest/.
- [Simakov2017] S. Simakov, et al., “Proposals for new measurements for IRDFF community and HPRL”, September 2017.
Review comment:
Entry Status:
Work in progress (as of SG-C review of May 2018)
Main references:
Please report any missing information to hprlinfo@oecd-nea.org
Experiments
- M. Majerle, P. Bem, et al., Au, Bi, Co and Nb cross-section measured by quasimonoenergetic neutrons from p+7Li reaction in the energy range of 18-36 MeV, Nuclear Physics A 953 (2016) 139
- M. Majerle, et al., Experimental Validation of IRDFF Cross-Sections in Quasi-MonoEnergetic Neutron Fluxes in 20-35 MeV Energy Range, IAEA report INDC(NDS)-0789, May 2019
Theory/Evaluation
Additional file attached:Simakov2017.pdf
Additional file attached:Co(n,xn).pdf
Request 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 KARLSRUHE, GER
Email: stanislav.simakov@partner.kit.edu
Project (context): IRDFF project
Impact:
The International Reactor Dosimetry and Fusion File (IRDFF) aims at providing evaluated neutron dosimetry reactions validated for all applications related to fission reactors and fusion technology development [IAEA2017].
Accuracy:
5%-10%
Justification document:
Accurate cross sections as well as spectrum-averaged cross sections (SACS) in relevant and well-characterized neutron fields are essential for improvement and validation of the evaluated data [Simakov2017].
Comment from requester:
The IRDFF project strives to evaluate, and eventually add to the library, high-threshold reactions with cross section plateaus located between 15/20 MeV and 100/150 MeV to meet the requirements of the accelerator-driven high-energy neutron sources. Note that it is important to know the cross section tail up to 100/150 MeV in order to allow the deconvolution of high-energy quasi-monoenergetic neutron source spectra.
References
- [IAEA2017] IAEA CRP on Testing and Improving the International Reactor Dosimetry and Fusion File (IRDFF),
http://www-nds.iaea.org/IRDFFtest/.
- [Simakov2017] S. Simakov, et al., “Proposals for new measurements for IRDFF community and HPRL”, September 2017.
Review comment:
Entry Status:
Work in progress (as of SG-C review of May 2018)
Main references:
Please report any missing information to hprlinfo@oecd-nea.org
Additional file attached:Simakov2017.pdf
Additional file attached:Pronyaev-nxn-high-en-dos.pdf
Request 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 KARLSRUHE, GER
Email: stanislav.simakov@partner.kit.edu
Project (context): IRDFF project
Impact:
The International Reactor Dosimetry and Fusion File (IRDFF) aims at providing evaluated neutron dosimetry reactions validated for all applications related to fission reactors and fusion technology development [IAEA2017].
Accuracy:
5%-10%
Justification document:
Accurate cross sections as well as spectrum-averaged cross sections (SACS) in relevant and well-characterized neutron fields are essential for improvement and validation of the evaluated data [Simakov2017].
Comment from requester:
The IRDFF project strives to evaluate, and eventually add to the library, high-threshold reactions with cross section plateaus located between 15/20 MeV and 100/150 MeV to meet the requirements of the accelerator-driven high-energy neutron sources. Note that it is important to know the cross section tail up to 100/150 MeV in order to allow the deconvolution of high-energy quasi-monoenergetic neutron source spectra.
References
- [IAEA2017] IAEA CRP on Testing and Improving the International Reactor Dosimetry and Fusion File (IRDFF),
http://www-nds.iaea.org/IRDFFtest/.
- [Simakov2017] S. Simakov, et al., “Proposals for new measurements for IRDFF community and HPRL”, September 2017.
Review comment:
Entry Status:
Work in progress (as of SG-C review of May 2018)
Main references:
Please report any missing information to hprlinfo@oecd-nea.org
Additional file attached:Simakov2017.pdf
Additional file attached:Pronyaev-nxn-high-en-dos.pdf
Request ID | 100 |
Type of the request | Special Purpose Quantity |
Target | Reaction and process | Incident Energy | Secondary energy or angle | Target uncertainty | Covariance |
92-U-235 | (n,f),(p,f) SIG | 100 MeV-500 MeV | | 5 | Y |
Field | Subfield | Date Request created | Date Request accepted | Ongoing action |
Standard | ADS | 23-MAR-18 | 11-APR-18 | Y |
Requester: Dr Roberto CAPOTE NOY at IAEA, AUT
Email: roberto.capotenoy@iaea.org
Project (context):
Impact:
Improvements in the standard cause all measurements relative to that standard to be improved. See Ref. [1].
Accuracy:
5% of the cross-section
Justification document:
There are discrepancies (see Fig. 24 in section III.E, pp.161-162 of Ref. [1]) between different theoretical calculations, data estimated from the (p,f) reaction, and the only measured data set of U-238(n,f) cross section at those energies [2]. New measurements of absolute cross sections of U-235 or U-238 (n,f) and/or U-235 or U-238 (p,f) reactions in the energy range where pion channels begin to play an important role (100-500 MeV) are needed to solve the discrepancies and to reduce the uncertainties of the Neutron Standards in that energy range.
References
- A.D. Carlson, et al., Evaluation of the Neutron Data Standards, Nuclear Data Sheets 148, 143-188 (2018)
- Z.W. Miller, A Measurement of the Prompt Fission Neutron Energy Spectrum for 235U(n,f) and the Neutron-induced Fission Cross Section for 238U(n,f), PhD Thesis, University of Kentucky (2015); https://uknowledge.uky.edu/physastron_etds/29/
Comment from requester:
At high-energy the (n,f) cross-section can be inferred with rather low uncertainty from (p,f) cross-section measurements, and thanks to this can be used in the neutron standards evaluation.
Review comment:
Entry Status:
Work in progress (as of SG-C review of May 2018)
Main references:
Please report any missing information to hprlinfo@oecd-nea.org
Experiments
- U-235 measurement performed at n_TOF in 2018
Theory/Evaluation
- B. Marcinkevicius, S. Simakov, V. Pronyaev, 209Bi(n,f) and natPb(n,f) cross sections as a new reference and extension of the 235U, 238U and 239Pu(n,f) standards up to 1 GeV, IAEA Report INDC(NDS)-0681
- A.D. Carlson et al., Evaluation of the Neutron Data Standards, NDS 148 (2018) 143
Additional file attached:
Additional file attached:
Request ID | 101 |
Type of the request | Special Purpose Quantity |
Target | Reaction and process | Incident Energy | Secondary energy or angle | Target uncertainty | Covariance |
92-U-238 | (n,f),(p,f) SIG | 100 MeV-500 MeV | | 5 | Y |
Field | Subfield | Date Request created | Date Request accepted | Ongoing action |
Standard | ADS | 23-MAR-18 | 11-APR-18 | Y |
Requester: Dr Roberto CAPOTE NOY at IAEA, AUT
Email: roberto.capotenoy@iaea.org
Project (context):
Impact:
Improvements in the standard cause all measurements relative to that standard to be improved. See Ref. [1].
Accuracy:
5% of the cross-section
Justification document:
There are discrepancies (see Fig. 24 in section III.E, pp.161-162 of Ref. [1]) between different theoretical calculations, data estimated from the (p,f) reaction, and the only measured data set of U-238(n,f) cross section at those energies [2]. New measurements of absolute cross sections of U-235 or U-238 (n,f) and/or U-235 or U-238 (p,f) reactions in the energy range where pion channels begin to play an important role (100-500 MeV) are needed to solve the discrepancies and to reduce the uncertainties of the Neutron Standards in that energy range.
References
- A.D. Carlson, et al., Evaluation of the Neutron Data Standards, Nuclear Data Sheets 148, 143-188 (2018)
- Z.W. Miller, A Measurement of the Prompt Fission Neutron Energy Spectrum for 235U(n,f) and the Neutron-induced Fission Cross Section for 238U(n,f), PhD Thesis, University of Kentucky (2015); https://uknowledge.uky.edu/physastron_etds/29/
Comment from requester:
At high-energy the (n,f) cross-section can be inferred with rather low uncertainty from (p,f) cross-section measurements, and thanks to this can be used in the neutron standards evaluation.
Review comment:
Entry Status:
Work in progress (as of SG-C review of May 2018)
Main references:
Please report any missing information to hprlinfo@oecd-nea.org
Theory/Evaluation
- B. Marcinkevicius, S. Simakov, V. Pronyaev, 209Bi(n,f) and natPb(n,f) cross sections as a new reference and extension of the 235U, 238U and 239Pu(n,f) standards up to 1 GeV, IAEA Report INDC(NDS)-0681
- A.D. Carlson et al., Evaluation of the Neutron Data Standards, NDS 148 (2018) 143
Additional file attached:
Additional file attached:
Request ID | 104 |
Type of the request | Special Purpose Quantity |
Target | Reaction and process | Incident Energy | Secondary energy or angle | Target uncertainty | Covariance |
9-F-19 | (n,2n) SIG,SPA | 239Pu(n,f) | | 3 | Y |
Field | Subfield | Date Request created | Date Request accepted | Ongoing action |
Fission | Dosimetry | 26-MAR-18 | 06-JUN-18 | |
Requester: Dr Roberto CAPOTE NOY at IAEA, AUT
Email: roberto.capotenoy@iaea.org
Project (context):
Impact:
A better knowledge of the prompt fission neutron spectrum (PFNS) from Pu-239 thermal-neutron induced fission is important for high-burnup fuels and new generation reactors. This is especially true when considering neutron radiation damage from the PFNS high-energy tail, which can be improved thanks to the measurements of spectrum-averaged cross section (SACS) of well-known high-threshold dosimetry reactions.
Deficiency in Pu-239(n,f) PFNS at large outgoing energies may be responsible for the discrepancies shown in Fig. 178 above 7.5 MeV of average reaction energy, see Fig. 178 in Ref. [1].
Accuracy:
3% cross-section ratio uncertainty relative to reference cross sections
Justification document:
No SACS measurements exist in Pu-239(nth,f) prompt neutron field. In the latest IAEA evaluation, the extrapolation of Pu-239(nth,f) PFNS to outgoing energies above 8 MeV is based on SACS estimated by interpolation between SACS measured in U-233, U-235 and Cf-252 prompt neutron fields, see page 74-76, Fig. 43 and Table XXVI in Ref. [2].
References
- D. Brown, et al., ENDF/B-VIII.0: The 8th Major Release of the Nuclear Reaction Data Library with CIELO-project Cross Sections, New Standards and Thermal Scattering Data, Nuclear Data Sheets 148 (2018) 1 (http://doi.org/10.1016/j.nds.2018.02.001)
- R. Capote et al., Prompt Fission Neutron Spectra of Actinides, Nuclear Data Sheets 131 (2016) 1 (http://doi.org/10.1016/j.nds.2015.12.002)
Comment from requester:
SACS measurements of high-threshold dosimetry reactions are requested to improve further the high-energy tail of Pu-239(nth,f) PFNS above 8 MeV of outgoing energy. These measurements should be performed relative to high-threshold reference cross sections: Al-27(n,a), Au-197(n,2n), Ni-58(n,p).
Review comment:
Entry Status:
Work in progress (as of SG-C review of June 2019)
Main references:
Please report any missing information to hprlinfo@oecd-nea.org
Additional file attached:
Additional file attached:
Request ID | 105 |
Type of the request | Special Purpose Quantity |
Target | Reaction and process | Incident Energy | Secondary energy or angle | Target uncertainty | Covariance |
25-MN-55 | (n,2n) SIG,SPA | 239Pu(n,f) | | 3 | Y |
Field | Subfield | Date Request created | Date Request accepted | Ongoing action |
Fission | Dosimetry | 26-MAR-18 | 06-JUN-18 | |
Requester: Dr Roberto CAPOTE NOY at IAEA, AUT
Email: roberto.capotenoy@iaea.org
Project (context):
Impact:
A better knowledge of the prompt fission neutron spectrum (PFNS) from Pu-239 thermal-neutron induced fission is important for high-burnup fuels and new generation reactors. This is especially true when considering neutron radiation damage from the PFNS high-energy tail, which can be improved thanks to the measurements of spectrum-averaged cross section (SACS) of well-known high-threshold dosimetry reactions.
Deficiency in Pu-239(n,f) PFNS at large outgoing energies may be responsible for the discrepancies shown in Fig. 178 above 7.5 MeV of average reaction energy, see Fig. 178 in Ref. [1].
Accuracy:
3% cross-section ratio uncertainty relative to reference cross sections
Justification document:
No SACS measurements exist in Pu-239(nth,f) prompt neutron field. In the latest IAEA evaluation, the extrapolation of Pu-239(nth,f) PFNS to outgoing energies above 8 MeV is based on SACS estimated by interpolation between SACS measured in U-233, U-235 and Cf-252 prompt neutron fields, see page 74-76, Fig. 43 and Table XXVI in Ref. [2].
References
- D. Brown, et al., ENDF/B-VIII.0: The 8th Major Release of the Nuclear Reaction Data Library with CIELO-project Cross Sections, New Standards and Thermal Scattering Data, Nuclear Data Sheets 148 (2018) 1 (http://doi.org/10.1016/j.nds.2018.02.001)
- R. Capote et al., Prompt Fission Neutron Spectra of Actinides, Nuclear Data Sheets 131 (2016) 1 (http://doi.org/10.1016/j.nds.2015.12.002)
Comment from requester:
SACS measurements of high-threshold dosimetry reactions are requested to improve further the high-energy tail of Pu-239(nth,f) PFNS above 8 MeV of outgoing energy. These measurements should be performed relative to high-threshold reference cross sections: Al-27(n,a), Au-197(n,2n), Ni-58(n,p).
Review comment:
Entry Status:
Work in progress (as of SG-C review of June 2019)
Main references:
Please report any missing information to hprlinfo@oecd-nea.org
Additional file attached:
Additional file attached:
Request ID | 106 |
Type of the request | Special Purpose Quantity |
Target | Reaction and process | Incident Energy | Secondary energy or angle | Target uncertainty | Covariance |
27-CO-59 | (n,2n) SIG,SPA | 239Pu(n,f) | | 3 | Y |
Field | Subfield | Date Request created | Date Request accepted | Ongoing action |
Fission | Dosimetry | 26-MAR-18 | 06-JUN-18 | |
Requester: Dr Roberto CAPOTE NOY at IAEA, AUT
Email: roberto.capotenoy@iaea.org
Project (context):
Impact:
A better knowledge of the prompt fission neutron spectrum (PFNS) from Pu-239 thermal-neutron induced fission is important for high-burnup fuels and new generation reactors. This is especially true when considering neutron radiation damage from the PFNS high-energy tail, which can be improved thanks to the measurements of spectrum-averaged cross section (SACS) of well-known high-threshold dosimetry reactions.
Deficiency in Pu-239(n,f) PFNS at large outgoing energies may be responsible for the discrepancies shown in Fig. 178 above 7.5 MeV of average reaction energy, see Fig. 178 in Ref. [1].
Accuracy:
3% cross-section ratio uncertainty relative to reference cross sections
Justification document:
No SACS measurements exist in Pu-239(nth,f) prompt neutron field. In the latest IAEA evaluation, the extrapolation of Pu-239(nth,f) PFNS to outgoing energies above 8 MeV is based on SACS estimated by interpolation between SACS measured in U-233, U-235 and Cf-252 prompt neutron fields, see page 74-76, Fig. 43 and Table XXVI in Ref. [2].
References
- D. Brown, et al., ENDF/B-VIII.0: The 8th Major Release of the Nuclear Reaction Data Library with CIELO-project Cross Sections, New Standards and Thermal Scattering Data, Nuclear Data Sheets 148 (2018) 1 (http://doi.org/10.1016/j.nds.2018.02.001)
- R. Capote et al., Prompt Fission Neutron Spectra of Actinides, Nuclear Data Sheets 131 (2016) 1 (http://doi.org/10.1016/j.nds.2015.12.002)
Comment from requester:
SACS measurements of high-threshold dosimetry reactions are requested to improve further the high-energy tail of Pu-239(nth,f) PFNS above 8 MeV of outgoing energy. These measurements should be performed relative to high-threshold reference cross sections: Al-27(n,a), Au-197(n,2n), Ni-58(n,p).
Review comment:
Entry Status:
Work in progress (as of SG-C review of June 2019)
Main references:
Please report any missing information to hprlinfo@oecd-nea.org
Additional file attached:
Additional file attached:
Request ID | 107 |
Type of the request | Special Purpose Quantity |
Target | Reaction and process | Incident Energy | Secondary energy or angle | Target uncertainty | Covariance |
28-NI-58 | (n,2n) SIG,SPA | 239Pu(n,f) | | 3 | Y |
Field | Subfield | Date Request created | Date Request accepted | Ongoing action |
Fission | Dosimetry | 26-MAR-18 | 06-JUN-18 | |
Requester: Dr Roberto CAPOTE NOY at IAEA, AUT
Email: roberto.capotenoy@iaea.org
Project (context):
Impact:
A better knowledge of the prompt fission neutron spectrum (PFNS) from Pu-239 thermal-neutron induced fission is important for high-burnup fuels and new generation reactors. This is especially true when considering neutron radiation damage from the PFNS high-energy tail, which can be improved thanks to the measurements of spectrum-averaged cross section (SACS) of well-known high-threshold dosimetry reactions.
Deficiency in Pu-239(n,f) PFNS at large outgoing energies may be responsible for the discrepancies shown in Fig. 178 above 7.5 MeV of average reaction energy, see Fig. 178 in Ref. [1].
Accuracy:
3% cross-section ratio uncertainty relative to reference cross sections
Justification document:
No SACS measurements exist in Pu-239(nth,f) prompt neutron field. In the latest IAEA evaluation, the extrapolation of Pu-239(nth,f) PFNS to outgoing energies above 8 MeV is based on SACS estimated by interpolation between SACS measured in U-233, U-235 and Cf-252 prompt neutron fields, see page 74-76, Fig. 43 and Table XXVI in Ref. [2].
References
- D. Brown, et al., ENDF/B-VIII.0: The 8th Major Release of the Nuclear Reaction Data Library with CIELO-project Cross Sections, New Standards and Thermal Scattering Data, Nuclear Data Sheets 148 (2018) 1 (http://doi.org/10.1016/j.nds.2018.02.001)
- R. Capote et al., Prompt Fission Neutron Spectra of Actinides, Nuclear Data Sheets 131 (2016) 1 (http://doi.org/10.1016/j.nds.2015.12.002)
Comment from requester:
SACS measurements of high-threshold dosimetry reactions are requested to improve further the high-energy tail of Pu-239(nth,f) PFNS above 8 MeV of outgoing energy. These measurements should be performed relative to high-threshold reference cross sections: Al-27(n,a), Au-197(n,2n), Ni-58(n,p).
Review comment:
Entry Status:
Work in progress (as of SG-C review of June 2019)
Main references:
Please report any missing information to hprlinfo@oecd-nea.org
Additional file attached:
Additional file attached:
Request ID | 108 |
Type of the request | Special Purpose Quantity |
Target | Reaction and process | Incident Energy | Secondary energy or angle | Target uncertainty | Covariance |
33-AS-75 | (n,2n) SIG,SPA | 239Pu(n,f) | | 3 | Y |
Field | Subfield | Date Request created | Date Request accepted | Ongoing action |
Fission | Dosimetry | 26-MAR-18 | 06-JUN-18 | |
Requester: Dr Roberto CAPOTE NOY at IAEA, AUT
Email: roberto.capotenoy@iaea.org
Project (context):
Impact:
A better knowledge of the prompt fission neutron spectrum (PFNS) from Pu-239 thermal-neutron induced fission is important for high-burnup fuels and new generation reactors. This is especially true when considering neutron radiation damage from the PFNS high-energy tail, which can be improved thanks to the measurements of spectrum-averaged cross section (SACS) of well-known high-threshold dosimetry reactions.
Deficiency in Pu-239(n,f) PFNS at large outgoing energies may be responsible for the discrepancies shown in Fig. 178 above 7.5 MeV of average reaction energy, see Fig. 178 in Ref. [1].
Accuracy:
3% cross-section ratio uncertainty relative to reference cross sections
Justification document:
No SACS measurements exist in Pu-239(nth,f) prompt neutron field. In the latest IAEA evaluation, the extrapolation of Pu-239(nth,f) PFNS to outgoing energies above 8 MeV is based on SACS estimated by interpolation between SACS measured in U-233, U-235 and Cf-252 prompt neutron fields, see page 74-76, Fig. 43 and Table XXVI in Ref. [2].
References
- D. Brown, et al., ENDF/B-VIII.0: The 8th Major Release of the Nuclear Reaction Data Library with CIELO-project Cross Sections, New Standards and Thermal Scattering Data, Nuclear Data Sheets 148 (2018) 1 (http://doi.org/10.1016/j.nds.2018.02.001)
- R. Capote et al., Prompt Fission Neutron Spectra of Actinides, Nuclear Data Sheets 131 (2016) 1 (http://doi.org/10.1016/j.nds.2015.12.002)
Comment from requester:
SACS measurements of high-threshold dosimetry reactions are requested to improve further the high-energy tail of Pu-239(nth,f) PFNS above 8 MeV of outgoing energy. These measurements should be performed relative to high-threshold reference cross sections: Al-27(n,a), Au-197(n,2n), Ni-58(n,p).
Review comment:
Entry Status:
Work in progress (as of SG-C review of June 2019)
Main references:
Please report any missing information to hprlinfo@oecd-nea.org
Additional file attached:
Additional file attached:
Request ID | 109 |
Type of the request | Special Purpose Quantity |
Target | Reaction and process | Incident Energy | Secondary energy or angle | Target uncertainty | Covariance |
39-Y-89 | (n,2n) SIG,SPA | 239Pu(n,f) | | 3 | Y |
Field | Subfield | Date Request created | Date Request accepted | Ongoing action |
Fission | Dosimetry | 26-MAR-18 | 06-JUN-18 | |
Requester: Dr Roberto CAPOTE NOY at IAEA, AUT
Email: roberto.capotenoy@iaea.org
Project (context):
Impact:
A better knowledge of the prompt fission neutron spectrum (PFNS) from Pu-239 thermal-neutron induced fission is important for high-burnup fuels and new generation reactors. This is especially true when considering neutron radiation damage from the PFNS high-energy tail, which can be improved thanks to the measurements of spectrum-averaged cross section (SACS) of well-known high-threshold dosimetry reactions.
Deficiency in Pu-239(n,f) PFNS at large outgoing energies may be responsible for the discrepancies shown in Fig. 178 above 7.5 MeV of average reaction energy, see Fig. 178 in Ref. [1].
Accuracy:
3% cross-section ratio uncertainty relative to reference cross sections
Justification document:
No SACS measurements exist in Pu-239(nth,f) prompt neutron field. In the latest IAEA evaluation, the extrapolation of Pu-239(nth,f) PFNS to outgoing energies above 8 MeV is based on SACS estimated by interpolation between SACS measured in U-233, U-235 and Cf-252 prompt neutron fields, see page 74-76, Fig. 43 and Table XXVI in Ref. [2].
References
- D. Brown, et al., ENDF/B-VIII.0: The 8th Major Release of the Nuclear Reaction Data Library with CIELO-project Cross Sections, New Standards and Thermal Scattering Data, Nuclear Data Sheets 148 (2018) 1 (http://doi.org/10.1016/j.nds.2018.02.001)
- R. Capote et al., Prompt Fission Neutron Spectra of Actinides, Nuclear Data Sheets 131 (2016) 1 (http://doi.org/10.1016/j.nds.2015.12.002)
Comment from requester:
SACS measurements of high-threshold dosimetry reactions are requested to improve further the high-energy tail of Pu-239(nth,f) PFNS above 8 MeV of outgoing energy. These measurements should be performed relative to high-threshold reference cross sections: Al-27(n,a), Au-197(n,2n), Ni-58(n,p).
Review comment:
Entry Status:
Work in progress (as of SG-C review of June 2019)
Main references:
Please report any missing information to hprlinfo@oecd-nea.org
Additional file attached:
Additional file attached:
Request ID | 110 |
Type of the request | Special Purpose Quantity |
Target | Reaction and process | Incident Energy | Secondary energy or angle | Target uncertainty | Covariance |
40-ZR-90 | (n,2n) SIG,SPA | 239Pu(n,f) | | 3 | Y |
Field | Subfield | Date Request created | Date Request accepted | Ongoing action |
Fission | Dosimetry | 26-MAR-18 | 06-JUN-18 | |
Requester: Dr Roberto CAPOTE NOY at IAEA, AUT
Email: roberto.capotenoy@iaea.org
Project (context):
Impact:
A better knowledge of the prompt fission neutron spectrum (PFNS) from Pu-239 thermal-neutron induced fission is important for high-burnup fuels and new generation reactors. This is especially true when considering neutron radiation damage from the PFNS high-energy tail, which can be improved thanks to the measurements of spectrum-averaged cross section (SACS) of well-known high-threshold dosimetry reactions.
Deficiency in Pu-239(n,f) PFNS at large outgoing energies may be responsible for the discrepancies shown in Fig. 178 above 7.5 MeV of average reaction energy, see Fig. 178 in Ref. [1].
Accuracy:
3% cross-section ratio uncertainty relative to reference cross sections
Justification document:
No SACS measurements exist in Pu-239(nth,f) prompt neutron field. In the latest IAEA evaluation, the extrapolation of Pu-239(nth,f) PFNS to outgoing energies above 8 MeV is based on SACS estimated by interpolation between SACS measured in U-233, U-235 and Cf-252 prompt neutron fields, see page 74-76, Fig. 43 and Table XXVI in Ref. [2].
References
- D. Brown, et al., ENDF/B-VIII.0: The 8th Major Release of the Nuclear Reaction Data Library with CIELO-project Cross Sections, New Standards and Thermal Scattering Data, Nuclear Data Sheets 148 (2018) 1 (http://doi.org/10.1016/j.nds.2018.02.001)
- R. Capote et al., Prompt Fission Neutron Spectra of Actinides, Nuclear Data Sheets 131 (2016) 1 (http://doi.org/10.1016/j.nds.2015.12.002)
Comment from requester:
SACS measurements of high-threshold dosimetry reactions are requested to improve further the high-energy tail of Pu-239(nth,f) PFNS above 8 MeV of outgoing energy. These measurements should be performed relative to high-threshold reference cross sections: Al-27(n,a), Au-197(n,2n), Ni-58(n,p).
Review comment:
Entry Status:
Work in progress (as of SG-C review of June 2019)
Main references:
Please report any missing information to hprlinfo@oecd-nea.org
Additional file attached:
Additional file attached:
Request ID | 111 |
Type of the request | Special Purpose Quantity |
Target | Reaction and process | Incident Energy | Secondary energy or angle | Target uncertainty | Covariance |
41-NB-93 | (n,2n)Nb-92m SIG,SPA | 239Pu(n,f) | | 3 | Y |
Field | Subfield | Date Request created | Date Request accepted | Ongoing action |
Fission | Dosimetry | 26-MAR-18 | 06-JUN-18 | |
Requester: Dr Roberto CAPOTE NOY at IAEA, AUT
Email: roberto.capotenoy@iaea.org
Project (context):
Impact:
A better knowledge of the prompt fission neutron spectrum (PFNS) from Pu-239 thermal-neutron induced fission is important for high-burnup fuels and new generation reactors. This is especially true when considering neutron radiation damage from the PFNS high-energy tail, which can be improved thanks to the measurements of spectrum-averaged cross section (SACS) of well-known high-threshold dosimetry reactions.
Deficiency in Pu-239(n,f) PFNS at large outgoing energies may be responsible for the discrepancies shown in Fig. 178 above 7.5 MeV of average reaction energy, see Fig. 178 in Ref. [1].
Accuracy:
3% cross-section ratio uncertainty relative to reference cross sections
Justification document:
No SACS measurements exist in Pu-239(nth,f) prompt neutron field. In the latest IAEA evaluation, the extrapolation of Pu-239(nth,f) PFNS to outgoing energies above 8 MeV is based on SACS estimated by interpolation between SACS measured in U-233, U-235 and Cf-252 prompt neutron fields, see page 74-76, Fig. 43 and Table XXVI in Ref. [2].
References
- D. Brown, et al., ENDF/B-VIII.0: The 8th Major Release of the Nuclear Reaction Data Library with CIELO-project Cross Sections, New Standards and Thermal Scattering Data, Nuclear Data Sheets 148 (2018) 1 (http://doi.org/10.1016/j.nds.2018.02.001)
- R. Capote et al., Prompt Fission Neutron Spectra of Actinides, Nuclear Data Sheets 131 (2016) 1 (http://doi.org/10.1016/j.nds.2015.12.002)
Comment from requester:
SACS measurements of high-threshold dosimetry reactions are requested to improve further the high-energy tail of Pu-239(nth,f) PFNS above 8 MeV of outgoing energy. These measurements should be performed relative to high-threshold reference cross sections: Al-27(n,a), Au-197(n,2n), Ni-58(n,p).
Review comment:
Entry Status:
Work in progress (as of SG-C review of June 2019)
Main references:
Please report any missing information to hprlinfo@oecd-nea.org
Additional file attached:
Additional file attached:
Request ID | 112 |
Type of the request | Special Purpose Quantity |
Target | Reaction and process | Incident Energy | Secondary energy or angle | Target uncertainty | Covariance |
53-I-127 | (n,2n) SIG,SPA | 239Pu(n,f) | | 3 | Y |
Field | Subfield | Date Request created | Date Request accepted | Ongoing action |
Fission | Dosimetry | 26-MAR-18 | 06-JUN-18 | |
Requester: Dr Roberto CAPOTE NOY at IAEA, AUT
Email: roberto.capotenoy@iaea.org
Project (context):
Impact:
A better knowledge of the prompt fission neutron spectrum (PFNS) from Pu-239 thermal-neutron induced fission is important for high-burnup fuels and new generation reactors. This is especially true when considering neutron radiation damage from the PFNS high-energy tail, which can be improved thanks to the measurements of spectrum-averaged cross section (SACS) of well-known high-threshold dosimetry reactions.
Deficiency in Pu-239(n,f) PFNS at large outgoing energies may be responsible for the discrepancies shown in Fig. 178 above 7.5 MeV of average reaction energy, see Fig. 178 in Ref. [1].
Accuracy:
3% cross-section ratio uncertainty relative to reference cross sections
Justification document:
No SACS measurements exist in Pu-239(nth,f) prompt neutron field. In the latest IAEA evaluation, the extrapolation of Pu-239(nth,f) PFNS to outgoing energies above 8 MeV is based on SACS estimated by interpolation between SACS measured in U-233, U-235 and Cf-252 prompt neutron fields, see page 74-76, Fig. 43 and Table XXVI in Ref. [2].
References
- D. Brown, et al., ENDF/B-VIII.0: The 8th Major Release of the Nuclear Reaction Data Library with CIELO-project Cross Sections, New Standards and Thermal Scattering Data, Nuclear Data Sheets 148 (2018) 1 (http://doi.org/10.1016/j.nds.2018.02.001)
- R. Capote et al., Prompt Fission Neutron Spectra of Actinides, Nuclear Data Sheets 131 (2016) 1 (http://doi.org/10.1016/j.nds.2015.12.002)
Comment from requester:
SACS measurements of high-threshold dosimetry reactions are requested to improve further the high-energy tail of Pu-239(nth,f) PFNS above 8 MeV of outgoing energy. These measurements should be performed relative to high-threshold reference cross sections: Al-27(n,a), Au-197(n,2n), Ni-58(n,p).
Review comment:
Entry Status:
Work in progress (as of SG-C review of June 2019)
Main references:
Please report any missing information to hprlinfo@oecd-nea.org
Additional file attached:
Additional file attached:
Request ID | 113 |
Type of the request | Special Purpose Quantity |
Target | Reaction and process | Incident Energy | Secondary energy or angle | Target uncertainty | Covariance |
69-TM-169 | (n,2n) SIG,SPA | 239Pu(n,f) | | 3 | Y |
Field | Subfield | Date Request created | Date Request accepted | Ongoing action |
Fission | Dosimetry | 26-MAR-18 | 06-JUN-18 | |
Requester: Dr Roberto CAPOTE NOY at IAEA, AUT
Email: roberto.capotenoy@iaea.org
Project (context):
Impact:
A better knowledge of the prompt fission neutron spectrum (PFNS) from Pu-239 thermal-neutron induced fission is important for high-burnup fuels and new generation reactors. This is especially true when considering neutron radiation damage from the PFNS high-energy tail, which can be improved thanks to the measurements of spectrum-averaged cross section (SACS) of well-known high-threshold dosimetry reactions.
Deficiency in Pu-239(n,f) PFNS at large outgoing energies may be responsible for the discrepancies shown in Fig. 178 above 7.5 MeV of average reaction energy, see Fig. 178 in Ref. [1].
Accuracy:
3% cross-section ratio uncertainty relative to reference cross sections
Justification document:
No SACS measurements exist in Pu-239(nth,f) prompt neutron field. In the latest IAEA evaluation, the extrapolation of Pu-239(nth,f) PFNS to outgoing energies above 8 MeV is based on SACS estimated by interpolation between SACS measured in U-233, U-235 and Cf-252 prompt neutron fields, see page 74-76, Fig. 43 and Table XXVI in Ref. [2].
References
- D. Brown, et al., ENDF/B-VIII.0: The 8th Major Release of the Nuclear Reaction Data Library with CIELO-project Cross Sections, New Standards and Thermal Scattering Data, Nuclear Data Sheets 148 (2018) 1 (http://doi.org/10.1016/j.nds.2018.02.001)
- R. Capote et al., Prompt Fission Neutron Spectra of Actinides, Nuclear Data Sheets 131 (2016) 1 (http://doi.org/10.1016/j.nds.2015.12.002)
Comment from requester:
SACS measurements of high-threshold dosimetry reactions are requested to improve further the high-energy tail of Pu-239(nth,f) PFNS above 8 MeV of outgoing energy. These measurements should be performed relative to high-threshold reference cross sections: Al-27(n,a), Au-197(n,2n), Ni-58(n,p).
Review comment:
Entry Status:
Work in progress (as of SG-C review of June 2019)
Main references:
Please report any missing information to hprlinfo@oecd-nea.org
Additional file attached:
Additional file attached: