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:
Accuracy:
Justification document:
Comment from requester: References
Review comment:
Entry Status:
Main references: Theory/Evaluation Additional file attached:Simakov2017.pdf
Requester: Dr Stanislav SIMAKOV at KARLSRUHE, GER
Project (context): IRDFF project
Impact:
Accuracy:
Justification document:
Comment from requester: References
Review comment:
Entry Status:
Main references: Experiments Theory/Evaluation Additional file attached:Simakov2017.pdf
Requester: Dr Stanislav SIMAKOV at KARLSRUHE, GER
Project (context): IRDFF project
Impact:
Accuracy:
Justification document:
Comment from requester: References
Review comment:
Entry Status:
Main references: Theory/Evaluation Additional file attached:Simakov2017.pdf
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].
5%-10%
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.
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.
http://www-nds.iaea.org/IRDFFtest/.
Work in progress (as of SG-C review of May 2018)
Please report any missing information to hprlinfo@oecd-nea.org
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
Email: stanislav.simakov@partner.kit.edu
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].
5%-10%
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.
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.
http://www-nds.iaea.org/IRDFFtest/.
Work in progress (as of SG-C review of May 2018)
Please report any missing information to hprlinfo@oecd-nea.org
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
Email: stanislav.simakov@partner.kit.edu
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].
5%-10%
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.
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.
http://www-nds.iaea.org/IRDFFtest/.
Work in progress (as of SG-C review of May 2018)
Please report any missing information to hprlinfo@oecd-nea.org
Additional file attached:Cf252U235_HighThreshold.pdf