Request ID43 Type of the request Special Purpose Quantity
TargetReaction and processIncident EnergySecondary energy or angleTarget uncertaintyCovariance
 1-H-1 (n,el) SIG,DA  10 MeV-20 MeV 4 pi 1-2 Y
FieldSubfieldDate Request createdDate Request acceptedOngoing action
 Standard impact on all subfields 29-APR-11 13-MAY-11 Y

Requester: Dr Allan D. CARLSON at NIST, USA
Email: allan.carlson@nist.gov

Project (context): NIST, Neutron Cross-Section Standards (www-nds.iaea.org/standards), CSEWG, WPEC

Impact:
This neutron cross section standard is perhaps the most important of the standards [1]. All of the other standards have been measured relative to it. Any improvement in this standard improves all standards and other cross sections that have been directly or indirectly measured relative to this standard. It helps form the basis of the neutron cross section libraries. There is very large leverage associated with improvements in this cross section. A problem at about 14 MeV is shown in reference [2].

[1] A.D. Carlson, et al., International Evaluation of Neutron Cross Section Standards, Nuclear Data Sheets 110 (2009) 3215-3324.
[2] N. Boukharouba, et al., Measurement of the n-p elastic scattering angular distribution at 14.9 MeV, Phys. Rev. C 82, 014001 (2010).
[3] N. Boukharouba, et al., Measurement of the n-p elastic scattering angular distribution at 10 MeV, Phys. Rev. C 65, 014004 (2001).

Accuracy:
1%-2% over most of the angular range. Very little data are available at small center-of-mass angles so the emphasis should be placed there.

Justification document:
The nature of the standards makes a simple answer to the question difficult. Since essentially all cross section data depend on the standards, any improvement in this standard will improve data for any neutronics calculation.
This neutron cross section standard is perhaps the most important of the standards. All of the other standards have been measured relative to it. Any improvement in this standard improves all standards and other cross sections that have been directly or indirectly measured relative to this standard. It helps form the basis of the neutron cross section libraries. There is very large leverage associated with improvements in this cross section.

Comment from requester:

Review comment:

Arjan Plompen: New measurement efforts should seriously consider measuring the angular distribution for the outgoing neutron at the incident energies of 10 and 14.9 MeV tackled by the Ohio University collaboration while covering the forward angles and with good overlap with those data at backward angle [2,3]. Ideally they should answer the question concerning the degree of the Legendre polynomial required for the targeted uncertainty and allow the coefficients to be established accurately.

Don Smith: [...] improvements in the standards can almost always be justified. The H(n,n)H standard is certainly an important one. [...] this impacts on all technical areas but certainly more so at higher energies, e.g., in the HE tail of the fission neutron spectrum (or for fusion applications) [...]

Mark Chadwick: The sensivity of many experiments to this cross section is essentially one.

Allan Carlson in response to questions raised by Arjan Plompen:

A) It is very difficult to make absolute measurements of the hydrogen angular distribution with high accuracy. Instead it is much easier to make relative measurements. But to normalize the relative data to the hydrogen total elastic cross section requires either a rather complete measurement of the relative angular distribution or very good models to assist in the extrapolation to the angular region that was not measured (in the reference [2,3]). [...] it must be emphasized that this normalization aspect is very important.

B) It is disturbing that there are differences of 0.5 to 1% between the Arndt et al. and ENDF/B-VII evaluations of the total elastic cross section in the 10-20 MeV energy region. Part of this is because of the databases being used in the evaluations. For example, the Abfalterer et al. data were not used in the Arndt PWA analysis but they were included in the Hale (ENDF/B-VII) work. They had significant weight in the Hale evaluation due to the small experimental uncertainties so the evaluation is similar to those data. [...] It would be very valuable if each group used exactly the same database and compared their results.

C) Improvements in measurements of the total cross section are also worthwhile. The most recent work has used TOF techniques with white sources. These measurements are good but I would suggest that making a measurement at a single point with a (nearly) monoenergetic source for which very good background measurements are possible could provide even smaller uncertainty. In the 50’s and 60’s, a number of total cross section measurements were made in the MeV energy region with fraction of a percent uncertainties. I expect we could probably do a little better now. Note the detailed process described in Fast Neutron Physics for accurate total cross section measurements. An important point for the total cross section work (but not for the angular distribution work) is a very accurate determination of the energy of the neutrons. An error of 20 keV in the energy scale for a 1 MeV cross section measurement causes about a 1% error in the cross section. This effect is less however at higher neutron energies.

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:
Additional file attached:



Request ID46 Type of the request Special Purpose Quantity
TargetReaction and processIncident EnergySecondary energy or angleTarget uncertaintyCovariance
 27-CO-59 (n,g) SIG,SPA  252Cf(sf)  2-5 Y
FieldSubfieldDate Request createdDate Request acceptedOngoing action
 Dosimetry Fast fission, D-T fusion 06-OCT-17 06-OCT-17 

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

Project (context): IRDFF project

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

Accuracy:
2%-5%

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

Comment from requester:
New measurements of the spectrum-averaged cross section are requested to solve C/E discrepancy. See SPA_CE_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:
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_Cf252.pdf



Request ID47 Type of the request Special Purpose Quantity
TargetReaction and processIncident EnergySecondary energy or angleTarget uncertaintyCovariance
 90-TH-232 (n,f) SIG,SPA  252Cf(sf)  2-5 Y
FieldSubfieldDate Request createdDate Request acceptedOngoing action
 Dosimetry Fast fission, D-T fusion 06-OCT-17 06-OCT-17 

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

Project (context): IRDFF project

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

Accuracy:
2%-5%

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

Comment from requester:
New measurements of the spectrum-averaged cross section are requested to solve C/E discrepancy. See SPA_CE_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:
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_Cf252.pdf



Request ID48 Type of the request Special Purpose Quantity
TargetReaction and processIncident EnergySecondary energy or angleTarget uncertaintyCovariance
 30-ZN-67 (n,p) SIG,SPA  252Cf(sf)  2-5 Y
FieldSubfieldDate Request createdDate Request acceptedOngoing action
 Dosimetry Fast 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 ID49 Type of the request Special Purpose Quantity
TargetReaction and processIncident EnergySecondary energy or angleTarget uncertaintyCovariance
 42-MO-92 (n,p)Nb-92m SIG,SPA  252Cf(sf)  2-5 Y
FieldSubfieldDate Request createdDate Request acceptedOngoing action
 Dosimetry Fast fission, D-T fusion 06-OCT-17 06-OCT-17 

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

Project (context): IRDFF project

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

Accuracy:
2%-5%

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

Comment from requester:
New measurements of the spectrum-averaged cross section are requested to solve C/E discrepancy. See SPA_CE_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 ID50 Type of the request Special Purpose Quantity
TargetReaction and processIncident EnergySecondary energy or angleTarget uncertaintyCovariance
 28-NI-60 (n,p) SIG,SPA  252Cf(sf)  2-5 Y
FieldSubfieldDate Request createdDate Request acceptedOngoing action
 Dosimetry Fast fission, D-T fusion 06-OCT-17 06-OCT-17 

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

Project (context): IRDFF project

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

Accuracy:
2%-5%

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

Comment from requester:
New measurements of the spectrum-averaged cross section are requested to solve C/E discrepancy. See SPA_CE_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 ID51 Type of the request Special Purpose Quantity
TargetReaction and processIncident EnergySecondary energy or angleTarget uncertaintyCovariance
 26-FE-54 (n,a) SIG,SPA  252Cf(sf)  2-5 Y
FieldSubfieldDate Request createdDate Request acceptedOngoing action
 Dosimetry Fast fission, D-T fusion 06-OCT-17 06-OCT-17 

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

Project (context): IRDFF project

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

Accuracy:
2%-5%

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

Comment from requester:
Measurements of the spectrum-averaged cross section are missing for validation purposes, 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 ID52 Type of the request Special Purpose Quantity
TargetReaction and processIncident EnergySecondary energy or angleTarget uncertaintyCovariance
 33-AS-75 (n,2n) SIG,SPA  252Cf(sf)  2-5 Y
FieldSubfieldDate Request createdDate Request acceptedOngoing action
 Dosimetry D-T fusion 06-OCT-17 06-OCT-17 

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

Project (context): IRDFF project

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

Accuracy:
2%-5%

Justification document:
Accurate cross sections as well as spectrum-averaged cross sections (SACS) in relevant and well-characterized neutron fields are essential for improvement and validation of the evaluated data [Simakov2017].
Following a recommendation from the IAEA Data Development Project on Neutron Standards [Pronyaev2013], the IRDFF project supports SACS measurements of high-threshold (above 10 MeV) dosimetry cross-sections in well-characterized 252Cf(sf) and 235U(nth,f) neutron fields in order to improve the cross sections and/or the high-energy part of the prompt fission neutron spectra.

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

References

  • [IAEA2017] IAEA CRP on Testing and Improving the International Reactor Dosimetry and Fusion File (IRDFF),
    http://www-nds.iaea.org/IRDFFtest/.
  • [Simakov2017] S. Simakov, et al., “Proposals for new measurements for IRDFF community and HPRL”, September 2017.
  • [Pronyaev2013] V.G. Pronyaev, A.D. Carlson and R. Capote Noy, “Toward a New Evaluation of Neutron Standards”, IAEA Technical Meeting, 8-12 July 2013, INDC(NDS)-0641.

Review comment:

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

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

Theory/Evaluation

Additional file attached:Simakov2017.pdf
Additional file attached:Cf252U235_HighThreshold.pdf



Request ID53 Type of the request Special Purpose Quantity
TargetReaction and processIncident EnergySecondary energy or angleTarget uncertaintyCovariance
 39-Y-89 (n,2n) SIG,SPA  252Cf(sf)  2-5 Y
FieldSubfieldDate Request createdDate Request acceptedOngoing action
 Dosimetry D-T fusion 06-OCT-17 06-OCT-17 

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

Project (context): IRDFF project

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

Accuracy:
2%-5%

Justification document:
Accurate cross sections as well as spectrum-averaged cross sections (SACS) in relevant and well-characterized neutron fields are essential for improvement and validation of the evaluated data [Simakov2017].
Following a recommendation from the IAEA Data Development Project on Neutron Standards [Pronyaev2013], the IRDFF project supports SACS measurements of high-threshold (above 10 MeV) dosimetry cross-sections in well-characterized 252Cf(sf) and 235U(nth,f) neutron fields in order to improve the cross sections and/or the high-energy part of the prompt fission neutron spectra.

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

References

  • [IAEA2017] IAEA CRP on Testing and Improving the International Reactor Dosimetry and Fusion File (IRDFF),
    http://www-nds.iaea.org/IRDFFtest/.
  • [Simakov2017] S. Simakov, et al., “Proposals for new measurements for IRDFF community and HPRL”, September 2017.
  • [Pronyaev2013] V.G. Pronyaev, A.D. Carlson and R. Capote Noy, “Toward a New Evaluation of Neutron Standards”, IAEA Technical Meeting, 8-12 July 2013, INDC(NDS)-0641.

Review comment:

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

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

Experiments

Theory/Evaluation

Validation

Additional file attached:Simakov2017.pdf
Additional file attached:Cf252U235_HighThreshold.pdf



Request ID54 Type of the request Special Purpose Quantity
TargetReaction and processIncident EnergySecondary energy or angleTarget uncertaintyCovariance
 25-MN-55 (n,g) SIG,SPA  235U(n,f)  2-5 Y
FieldSubfieldDate Request createdDate Request acceptedOngoing action
 Dosimetry Fast fission, D-T fusion 06-OCT-17 06-OCT-17 

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

Project (context): IRDFF project

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

Accuracy:
2%-5%

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

Comment from requester:
New measurements of the spectrum-averaged cross section are requested to solve C/E discrepancy. See SPA_CE_U235.pdf below.

References

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

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

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

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

Theory/Evaluation

Additional file attached:Simakov2017.pdf
Additional file attached:SPA_CE_U235.pdf



Request ID55 Type of the request Special Purpose Quantity
TargetReaction and processIncident EnergySecondary energy or angleTarget uncertaintyCovariance
 92-U-238 (n,g) SIG,SPA  235U(n,f)  2-5 Y
FieldSubfieldDate Request createdDate Request acceptedOngoing action
 Dosimetry Fast fission, D-T fusion 06-OCT-17 06-OCT-17 

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

Project (context): IRDFF project

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

Accuracy:
2%-5%

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

Comment from requester:
New measurements of the spectrum-averaged cross section are requested to solve C/E discrepancy. See SPA_CE_U235.pdf below.

References

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

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

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

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

Theory/Evaluation

Additional file attached:Simakov2017.pdf
Additional file attached:SPA_CE_U235.pdf



Request ID56 Type of the request Special Purpose Quantity
TargetReaction and processIncident EnergySecondary energy or angleTarget uncertaintyCovariance
 29-CU-63 (n,g) SIG,SPA  235U(n,f)  2-5 Y
FieldSubfieldDate Request createdDate Request acceptedOngoing action
 Dosimetry Fast fission, D-T fusion 06-OCT-17 06-OCT-17 

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

Project (context): IRDFF project

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

Accuracy:
2%-5%

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

Comment from requester:
New measurements of the spectrum-averaged cross section are requested to solve C/E discrepancy. See SPA_CE_U235.pdf below.

References

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

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

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

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

Theory/Evaluation

Additional file attached:Simakov2017.pdf
Additional file attached:SPA_CE_U235.pdf



Request ID57 Type of the request Special Purpose Quantity
TargetReaction and processIncident EnergySecondary energy or angleTarget uncertaintyCovariance
 57-LA-139 (n,g) SIG,SPA  235U(n,f)  2-5 Y
FieldSubfieldDate Request createdDate Request acceptedOngoing action
 Dosimetry Fast fission, D-T fusion 06-OCT-17 06-OCT-17 

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

Project (context): IRDFF project

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

Accuracy:
2%-5%

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

Comment from requester:
New measurements of the spectrum-averaged cross section are requested to solve C/E discrepancy. See SPA_CE_U235.pdf below.

References

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

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

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

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

Theory/Evaluation

Additional file attached:Simakov2017.pdf
Additional file attached:SPA_CE_U235.pdf



Request ID58 Type of the request Special Purpose Quantity
TargetReaction and processIncident EnergySecondary energy or angleTarget uncertaintyCovariance
 45-RH-103 (n,inl)Rh-103m SIG,SPA  235U(n,f)  2-5 Y
FieldSubfieldDate Request createdDate Request acceptedOngoing action
 Dosimetry Fast fission, D-T fusion 06-OCT-17 06-OCT-17 

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

Project (context): IRDFF project

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

Accuracy:
2%-5%

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

Comment from requester:
New measurements of the spectrum-averaged cross section are requested to solve C/E discrepancy. See SPA_CE_U235.pdf below.

References

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

Review comment:

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

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

Experiments

Theory/Evaluation

Additional file attached:Simakov2017.pdf
Additional file attached:SPA_CE_U235.pdf



Request ID59 Type of the request Special Purpose Quantity
TargetReaction and processIncident EnergySecondary energy or angleTarget uncertaintyCovariance
 69-TM-169 (n,2n) SIG,SPA  235U(n,f)  2-5 Y
FieldSubfieldDate Request createdDate Request acceptedOngoing action
 Dosimetry D-T fusion 06-OCT-17 06-OCT-17 

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

Project (context): IRDFF project

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

Accuracy:
2%-5%

Justification document:
Accurate cross sections as well as spectrum-averaged cross sections (SACS) in relevant and well-characterized neutron fields are essential for improvement and validation of the evaluated data [Simakov2017].
Following a recommendation from the IAEA Data Development Project on Neutron Standards [Pronyaev2013], the IRDFF project supports SACS measurements of high-threshold (above 10 MeV) dosimetry cross-sections in well-characterized 252Cf(sf) and 235U(nth,f) neutron fields in order to improve the cross sections and/or the high-energy part of the prompt fission neutron spectra.

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

References

  • [IAEA2017] IAEA CRP on Testing and Improving the International Reactor Dosimetry and Fusion File (IRDFF),
    http://www-nds.iaea.org/IRDFFtest/.
  • [Simakov2017] S. Simakov, et al., “Proposals for new measurements for IRDFF community and HPRL”, September 2017.
  • [Pronyaev2013] V.G. Pronyaev, A.D. Carlson and R. Capote Noy, “Toward a New Evaluation of Neutron Standards”, IAEA Technical Meeting, 8-12 July 2013, INDC(NDS)-0641.

Review comment:

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

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

Theory/Evaluation

Additional file attached:Simakov2017.pdf
Additional file attached:CE_U235_and_HighThreshold.pdf



Request ID60 Type of the request Special Purpose Quantity
TargetReaction and processIncident EnergySecondary energy or angleTarget uncertaintyCovariance
 29-CU-65 (n,2n) SIG,SPA  235U(n,f)  2-5 Y
FieldSubfieldDate Request createdDate Request acceptedOngoing action
 Dosimetry D-T fusion 06-OCT-17 06-OCT-17 

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

Project (context): IRDFF project

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

Accuracy:
2%-5%

Justification document:
Accurate cross sections as well as spectrum-averaged cross sections (SACS) in relevant and well-characterized neutron fields are essential for improvement and validation of the evaluated data [Simakov2017].
Following a recommendation from the IAEA Data Development Project on Neutron Standards [Pronyaev2013], the IRDFF project supports SACS measurements of high-threshold (above 10 MeV) dosimetry cross-sections in well-characterized 252Cf(sf) and 235U(nth,f) neutron fields in order to improve the cross sections and/or the high-energy part of the prompt fission neutron spectra.

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

References

  • [IAEA2017] IAEA CRP on Testing and Improving the International Reactor Dosimetry and Fusion File (IRDFF),
    http://www-nds.iaea.org/IRDFFtest/.
  • [Simakov2017] S. Simakov, et al., “Proposals for new measurements for IRDFF community and HPRL”, September 2017.
  • [Pronyaev2013] V.G. Pronyaev, A.D. Carlson and R. Capote Noy, “Toward a New Evaluation of Neutron Standards”, IAEA Technical Meeting, 8-12 July 2013, INDC(NDS)-0641.

Review comment:

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

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

Theory/Evaluation

Additional file attached:Simakov2017.pdf
Additional file attached:Cf252U235_HighThreshold.pdf



Request ID61 Type of the request Special Purpose Quantity
TargetReaction and processIncident EnergySecondary energy or angleTarget uncertaintyCovariance
 25-MN-55 (n,2n) SIG,SPA  235U(n,f)  2-5 Y
FieldSubfieldDate Request createdDate Request acceptedOngoing action
 Dosimetry D-T fusion 06-OCT-17 06-OCT-17 

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

Project (context): IRDFF project

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

Accuracy:
2%-5%

Justification document:
Accurate cross sections as well as spectrum-averaged cross sections (SACS) in relevant and well-characterized neutron fields are essential for improvement and validation of the evaluated data [Simakov2017].
Following a recommendation from the IAEA Data Development Project on Neutron Standards [Pronyaev2013], the IRDFF project supports SACS measurements of high-threshold (above 10 MeV) dosimetry cross-sections in well-characterized 252Cf(sf) and 235U(nth,f) neutron fields in order to improve the cross sections and/or the high-energy part of the prompt fission neutron spectra.

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

References

  • [IAEA2017] IAEA CRP on Testing and Improving the International Reactor Dosimetry and Fusion File (IRDFF),
    http://www-nds.iaea.org/IRDFFtest/.
  • [Simakov2017] S. Simakov, et al., “Proposals for new measurements for IRDFF community and HPRL”, September 2017.
  • [Pronyaev2013] V.G. Pronyaev, A.D. Carlson and R. Capote Noy, “Toward a New Evaluation of Neutron Standards”, IAEA Technical Meeting, 8-12 July 2013, INDC(NDS)-0641.

Review comment:

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

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

Experiments

Theory/Evaluation

Additional file attached:Simakov2017.pdf
Additional file attached:SPA_CE_U235.pdf



Request ID62 Type of the request Special Purpose Quantity
TargetReaction and processIncident EnergySecondary energy or angleTarget uncertaintyCovariance
 28-NI-58 (n,2n) SIG,SPA  235U(n,f)  2-5 Y
FieldSubfieldDate Request createdDate Request acceptedOngoing action
 Dosimetry D-T fusion 06-OCT-17 06-OCT-17 

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

Project (context): IRDFF project

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

Accuracy:
2%-5%

Justification document:
Accurate cross sections as well as spectrum-averaged cross sections (SACS) in relevant and well-characterized neutron fields are essential for improvement and validation of the evaluated data [Simakov2017].
Following a recommendation from the IAEA Data Development Project on Neutron Standards [Pronyaev2013], the IRDFF project supports SACS measurements of high-threshold (above 10 MeV) dosimetry cross-sections in well-characterized 252Cf(sf) and 235U(nth,f) neutron fields in order to improve the cross sections and/or the high-energy part of the prompt fission neutron spectra.

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

References

  • [IAEA2017] IAEA CRP on Testing and Improving the International Reactor Dosimetry and Fusion File (IRDFF),
    http://www-nds.iaea.org/IRDFFtest/.
  • [Simakov2017] S. Simakov, et al., “Proposals for new measurements for IRDFF community and HPRL”, September 2017.
  • [Pronyaev2013] V.G. Pronyaev, A.D. Carlson and R. Capote Noy, “Toward a New Evaluation of Neutron Standards”, IAEA Technical Meeting, 8-12 July 2013, INDC(NDS)-0641.

Review comment:

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

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

Theory/Evaluation

Additional file attached:Simakov2017.pdf
Additional file attached:SPA_CE_U235.pdf



Request ID63 Type of the request Special Purpose Quantity
TargetReaction and processIncident EnergySecondary energy or angleTarget uncertaintyCovariance
 95-AM-241 (n,f) SIG,SPA  252Cf(sf)-235U(n,f)  2-5 Y
FieldSubfieldDate Request createdDate Request acceptedOngoing action
 Dosimetry Fast fission, D-T fusion 06-OCT-17 06-OCT-17 

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

Project (context): IRDFF project

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

Accuracy:
2%-5%

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

Comment from requester:
Measurements of the spectrum-averaged cross section are missing for validation purposes.

References

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

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

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

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

Theory/Evaluation

Additional file attached:Simakov2017.pdf
Additional file attached:



Request ID64 Type of the request Special Purpose Quantity
TargetReaction and processIncident EnergySecondary energy or angleTarget uncertaintyCovariance
 15-P-31 (n,p) SIG,SPA  252Cf(sf)-235U(n,f)  2-5 Y
FieldSubfieldDate Request createdDate Request acceptedOngoing action
 Dosimetry Fast fission, D-T fusion 06-OCT-17 06-OCT-17 

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

Project (context): IRDFF project

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

Accuracy:
2%-5%

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

Comment from requester:
Measurements of the 252Cf(sf)-spectrum-averaged cross section are missing for validation purposes. New measurements of the 235U(n,f)-spectrum-averaged cross section are requested to solve C/E discrepancy. See SPA_CE_Cf252U235.pdf below.

References

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

Review comment:

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

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

Theory/Evaluation

Additional file attached:Simakov2017.pdf
Additional file attached:SPA_CE_Cf252U235.pdf



Request ID65 Type of the request Special Purpose Quantity
TargetReaction and processIncident EnergySecondary energy or angleTarget uncertaintyCovariance
 92-U-238 (n,2n) SIG,SPA  252Cf(sf)-235U(n,f)  2-5 Y
FieldSubfieldDate Request createdDate Request acceptedOngoing action
 Dosimetry Fast fission, D-T fusion 06-OCT-17 06-OCT-17 

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

Project (context): IRDFF project

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

Accuracy:
2%-5%

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

Comment from requester:
New measurements of the spectrum-averaged cross section are requested to solve C/E discrepancy and for improvement of the prompt fission neutron spectrum at high energy. See CE_Cf252U235_and_HighThreshold.pdf below.

References

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

Review comment:

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

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

Theory/Evaluation

Additional file attached:Simakov2017.pdf
Additional file attached:CE_Cf252U235_and_HighThreshold.pdf



Request ID66 Type of the request Special Purpose Quantity
TargetReaction and processIncident EnergySecondary energy or angleTarget uncertaintyCovariance
 49-IN-115 (n,2n)In-114m SIG,SPA  252Cf(sf)-235U(n,f)  2-5 Y
FieldSubfieldDate Request createdDate Request acceptedOngoing action
 Dosimetry D-T fusion 06-OCT-17 06-OCT-17 

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

Project (context): IRDFF project

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

Accuracy:
2%-5%

Justification document:
Accurate cross sections as well as spectrum-averaged cross sections (SACS) in relevant and well-characterized neutron fields are essential for improvement and validation of the evaluated data [Simakov2017].
Following a recommendation from the IAEA Data Development Project on Neutron Standards [Pronyaev2013], the IRDFF project supports SACS measurements of high-threshold (above 10 MeV) dosimetry cross-sections in well-characterized 252Cf(sf) and 235U(nth,f) neutron fields in order to improve the cross sections and/or the high-energy part of the prompt fission neutron spectra.

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

References

  • [IAEA2017] IAEA CRP on Testing and Improving the International Reactor Dosimetry and Fusion File (IRDFF),
    http://www-nds.iaea.org/IRDFFtest/.
  • [Simakov2017] S. Simakov, et al., “Proposals for new measurements for IRDFF community and HPRL”, September 2017.
  • [Pronyaev2013] V.G. Pronyaev, A.D. Carlson and R. Capote Noy, “Toward a New Evaluation of Neutron Standards”, IAEA Technical Meeting, 8-12 July 2013, INDC(NDS)-0641.

Review comment:

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

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

Theory/Evaluation

Additional file attached:Simakov2017.pdf
Additional file attached:Cf252U235_HighThreshold.pdf



Request ID67 Type of the request Special Purpose Quantity
TargetReaction and processIncident EnergySecondary energy or angleTarget uncertaintyCovariance
 59-PR-141 (n,2n) SIG,SPA  252Cf(sf)-235U(n,f)  2-5 Y
FieldSubfieldDate Request createdDate Request acceptedOngoing action
 Dosimetry D-T fusion 06-OCT-17 06-OCT-17 

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

Project (context): IRDFF project

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

Accuracy:
2%-5%

Justification document:
Accurate cross sections as well as spectrum-averaged cross sections (SACS) in relevant and well-characterized neutron fields are essential for improvement and validation of the evaluated data [Simakov2017].
Following a recommendation from the IAEA Data Development Project on Neutron Standards [Pronyaev2013], the IRDFF project supports SACS measurements of high-threshold (above 10 MeV) dosimetry cross-sections in well-characterized 252Cf(sf) and 235U(nth,f) neutron fields in order to improve the cross sections and/or the high-energy part of the prompt fission neutron spectra.

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

References

  • [IAEA2017] IAEA CRP on Testing and Improving the International Reactor Dosimetry and Fusion File (IRDFF),
    http://www-nds.iaea.org/IRDFFtest/.
  • [Simakov2017] S. Simakov, et al., “Proposals for new measurements for IRDFF community and HPRL”, September 2017.
  • [Pronyaev2013] V.G. Pronyaev, A.D. Carlson and R. Capote Noy, “Toward a New Evaluation of Neutron Standards”, IAEA Technical Meeting, 8-12 July 2013, INDC(NDS)-0641.

Review comment:

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

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

Theory/Evaluation

Additional file attached:Simakov2017.pdf
Additional file attached:Cf252U235_HighThreshold.pdf



Request ID68 Type of the request Special Purpose Quantity
TargetReaction and processIncident EnergySecondary energy or angleTarget uncertaintyCovariance
 24-CR-52 (n,2n) SIG,SPA  252Cf(sf)-235U(n,f)  2-5 Y
FieldSubfieldDate Request createdDate Request acceptedOngoing action
 Dosimetry D-T fusion 06-OCT-17 06-OCT-17 

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

Project (context): IRDFF project

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

Accuracy:
2%-5%

Justification document:
Accurate cross sections as well as spectrum-averaged cross sections (SACS) in relevant and well-characterized neutron fields are essential for improvement and validation of the evaluated data [Simakov2017].
Following a recommendation from the IAEA Data Development Project on Neutron Standards [Pronyaev2013], the IRDFF project supports SACS measurements of high-threshold (above 10 MeV) dosimetry cross-sections in well-characterized 252Cf(sf) and 235U(nth,f) neutron fields in order to improve the cross sections and/or the high-energy part of the prompt fission neutron spectra.

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

References

  • [IAEA2017] IAEA CRP on Testing and Improving the International Reactor Dosimetry and Fusion File (IRDFF),
    http://www-nds.iaea.org/IRDFFtest/.
  • [Simakov2017] S. Simakov, et al., “Proposals for new measurements for IRDFF community and HPRL”, September 2017.
  • [Pronyaev2013] V.G. Pronyaev, A.D. Carlson and R. Capote Noy, “Toward a New Evaluation of Neutron Standards”, IAEA Technical Meeting, 8-12 July 2013, INDC(NDS)-0641.

Review comment:

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

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

Theory/Evaluation

Additional file attached:Simakov2017.pdf
Additional file attached:Cf252U235_HighThreshold.pdf



Request ID69 Type of the request Special Purpose Quantity
TargetReaction and processIncident EnergySecondary energy or angleTarget uncertaintyCovariance
 11-NA-23 (n,2n) SIG,SPA  252Cf(sf)-235U(n,f)  2-5 Y
FieldSubfieldDate Request createdDate Request acceptedOngoing action
 Dosimetry D-T fusion 06-OCT-17 06-OCT-17 

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

Project (context): IRDFF project

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

Accuracy:
2%-5%

Justification document:
Accurate cross sections as well as spectrum-averaged cross sections (SACS) in relevant and well-characterized neutron fields are essential for improvement and validation of the evaluated data [Simakov2017].
Following a recommendation from the IAEA Data Development Project on Neutron Standards [Pronyaev2013], the IRDFF project supports SACS measurements of high-threshold (above 10 MeV) dosimetry cross-sections in well-characterized 252Cf(sf) and 235U(nth,f) neutron fields in order to improve the cross sections and/or the high-energy part of the prompt fission neutron spectra.

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

References

  • [IAEA2017] IAEA CRP on Testing and Improving the International Reactor Dosimetry and Fusion File (IRDFF),
    http://www-nds.iaea.org/IRDFFtest/.
  • [Simakov2017] S. Simakov, et al., “Proposals for new measurements for IRDFF community and HPRL”, September 2017.
  • [Pronyaev2013] V.G. Pronyaev, A.D. Carlson and R. Capote Noy, “Toward a New Evaluation of Neutron Standards”, IAEA Technical Meeting, 8-12 July 2013, INDC(NDS)-0641.

Review comment:

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

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

Experiments

Theory/Evaluation

Additional file attached:Simakov2017.pdf
Additional file attached:Cf252U235_HighThreshold.pdf



Request ID70 Type of the request Special Purpose Quantity
TargetReaction and processIncident EnergySecondary energy or angleTarget uncertaintyCovariance
 13-AL-27 (n,2n) SIG,SPA  252Cf(sf)-235U(n,f)  2-5 Y
FieldSubfieldDate Request createdDate Request acceptedOngoing action
 Dosimetry D-T fusion 06-OCT-17 06-OCT-17 

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

Project (context): IRDFF project

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

Accuracy:
2%-5%

Justification document:
Accurate cross sections as well as spectrum-averaged cross sections (SACS) in relevant and well-characterized neutron fields are essential for improvement and validation of the evaluated data [Simakov2017].
Following a recommendation from the IAEA Data Development Project on Neutron Standards [Pronyaev2013], the IRDFF project supports SACS measurements of high-threshold (above 10 MeV) dosimetry cross-sections in well-characterized 252Cf(sf) and 235U(nth,f) neutron fields in order to improve the cross sections and/or the high-energy part of the prompt fission neutron spectra.

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

References

  • [IAEA2017] IAEA CRP on Testing and Improving the International Reactor Dosimetry and Fusion File (IRDFF),
    http://www-nds.iaea.org/IRDFFtest/.
  • [Simakov2017] S. Simakov, et al., “Proposals for new measurements for IRDFF community and HPRL”, September 2017.
  • [Pronyaev2013] V.G. Pronyaev, A.D. Carlson and R. Capote Noy, “Toward a New Evaluation of Neutron Standards”, IAEA Technical Meeting, 8-12 July 2013, INDC(NDS)-0641.

Review comment:

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

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

Theory/Evaluation

Additional file attached:Simakov2017.pdf
Additional file attached:Cf252U235_HighThreshold.pdf



Request ID71 Type of the request Special Purpose Quantity
TargetReaction and processIncident EnergySecondary energy or angleTarget uncertaintyCovariance
 22-TI-46 (n,2n) SIG,SPA  252Cf(sf)-235U(n,f)  2-5 Y
FieldSubfieldDate Request createdDate Request acceptedOngoing action
 Dosimetry D-T fusion 06-OCT-17 06-OCT-17 

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

Project (context): IRDFF project

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

Accuracy:
2%-5%

Justification document:
Accurate cross sections as well as spectrum-averaged cross sections (SACS) in relevant and well-characterized neutron fields are essential for improvement and validation of the evaluated data [Simakov2017].
Following a recommendation from the IAEA Data Development Project on Neutron Standards [Pronyaev2013], the IRDFF project supports SACS measurements of high-threshold (above 10 MeV) dosimetry cross-sections in well-characterized 252Cf(sf) and 235U(nth,f) neutron fields in order to improve the cross sections and/or the high-energy part of the prompt fission neutron spectra.

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

References

  • [IAEA2017] IAEA CRP on Testing and Improving the International Reactor Dosimetry and Fusion File (IRDFF),
    http://www-nds.iaea.org/IRDFFtest/.
  • [Simakov2017] S. Simakov, et al., “Proposals for new measurements for IRDFF community and HPRL”, September 2017.
  • [Pronyaev2013] V.G. Pronyaev, A.D. Carlson and R. Capote Noy, “Toward a New Evaluation of Neutron Standards”, IAEA Technical Meeting, 8-12 July 2013, INDC(NDS)-0641.

Review comment:

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

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

Theory/Evaluation

Additional file attached:Simakov2017.pdf
Additional file attached:CE_Cf252U235_and_HighThreshold.pdf



Request ID72 Type of the request Special Purpose Quantity
TargetReaction and processIncident EnergySecondary energy or angleTarget uncertaintyCovariance
 50-SN-117 (n,inl)Sn-117m SIG,SPA  252Cf(sf)-235U(n,f)  2-5 Y
FieldSubfieldDate Request createdDate Request acceptedOngoing action
 Dosimetry Fast fission, D-T fusion 06-OCT-17 06-OCT-17 

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

Project (context): IRDFF project

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

Accuracy:
2%-5%

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

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

References

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

Review comment:

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

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

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



Request ID73 Type of the request Special Purpose Quantity
TargetReaction and processIncident EnergySecondary energy or angleTarget uncertaintyCovariance
 22-TI-47 (n,np) SIG,SPA  252Cf(sf)-235U(n,f)  5-10 Y
FieldSubfieldDate Request createdDate Request acceptedOngoing action
 Dosimetry D-T fusion, high-energy 06-OCT-17 06-OCT-17 

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

Project (context): IRDFF project

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

Accuracy:
5%-10%

Justification document:
Accurate cross sections as well as spectrum-averaged cross sections (SACS) in relevant and well-characterized neutron fields are essential for improvement and validation of the evaluated data [Simakov2017].
Following a recommendation from the IAEA Data Development Project on Neutron Standards [Pronyaev2013], the IRDFF project supports SACS measurements of high-threshold (above 10 MeV) dosimetry cross-sections in well-characterized 252Cf(sf) and 235U(nth,f) neutron fields in order to improve the cross sections and/or the high-energy part of the prompt fission neutron spectra.

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

References

  • [IAEA2017] IAEA CRP on Testing and Improving the International Reactor Dosimetry and Fusion File (IRDFF),
    http://www-nds.iaea.org/IRDFFtest/.
  • [Simakov2017] S. Simakov, et al., “Proposals for new measurements for IRDFF community and HPRL”, September 2017.
  • [Pronyaev2013] V.G. Pronyaev, A.D. Carlson and R. Capote Noy, “Toward a New Evaluation of Neutron Standards”, IAEA Technical Meeting, 8-12 July 2013, INDC(NDS)-0641.

Review comment:

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

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

Theory/Evaluation

Additional file attached:Simakov2017.pdf
Additional file attached:



Request ID74 Type of the request Special Purpose Quantity
TargetReaction and processIncident EnergySecondary energy or angleTarget uncertaintyCovariance
 22-TI-48 (n,np) SIG,SPA  252Cf(sf)-235U(n,f)  5-10 Y
FieldSubfieldDate Request createdDate Request acceptedOngoing action
 Dosimetry D-T fusion, high-energy 06-OCT-17 06-OCT-17 

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

Project (context): IRDFF project

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

Accuracy:
5%-10%

Justification document:
Accurate cross sections as well as spectrum-averaged cross sections (SACS) in relevant and well-characterized neutron fields are essential for improvement and validation of the evaluated data [Simakov2017].
Following a recommendation from the IAEA Data Development Project on Neutron Standards [Pronyaev2013], the IRDFF project supports SACS measurements of high-threshold (above 10 MeV) dosimetry cross-sections in well-characterized 252Cf(sf) and 235U(nth,f) neutron fields in order to improve the cross sections and/or the high-energy part of the prompt fission neutron spectra.

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

References

  • [IAEA2017] IAEA CRP on Testing and Improving the International Reactor Dosimetry and Fusion File (IRDFF),
    http://www-nds.iaea.org/IRDFFtest/.
  • [Simakov2017] S. Simakov, et al., “Proposals for new measurements for IRDFF community and HPRL”, September 2017.
  • [Pronyaev2013] V.G. Pronyaev, A.D. Carlson and R. Capote Noy, “Toward a New Evaluation of Neutron Standards”, IAEA Technical Meeting, 8-12 July 2013, INDC(NDS)-0641.

Review comment:

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

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

Theory/Evaluation

Additional file attached:Simakov2017.pdf
Additional file attached:



Request ID75 Type of the request Special Purpose Quantity
TargetReaction and processIncident EnergySecondary energy or angleTarget uncertaintyCovariance
 22-TI-49 (n,np) SIG,SPA  252Cf(sf)-235U(n,f)  5-10 Y
FieldSubfieldDate Request createdDate Request acceptedOngoing action
 Dosimetry D-T fusion, high-energy 06-OCT-17 06-OCT-17 

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

Project (context): IRDFF project

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

Accuracy:
5%-10%

Justification document:
Accurate cross sections as well as spectrum-averaged cross sections (SACS) in relevant and well-characterized neutron fields are essential for improvement and validation of the evaluated data [Simakov2017].
Following a recommendation from the IAEA Data Development Project on Neutron Standards [Pronyaev2013], the IRDFF project supports SACS measurements of high-threshold (above 10 MeV) dosimetry cross-sections in well-characterized 252Cf(sf) and 235U(nth,f) neutron fields in order to improve the cross sections and/or the high-energy part of the prompt fission neutron spectra.

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

References

  • [IAEA2017] IAEA CRP on Testing and Improving the International Reactor Dosimetry and Fusion File (IRDFF),
    http://www-nds.iaea.org/IRDFFtest/.
  • [Simakov2017] S. Simakov, et al., “Proposals for new measurements for IRDFF community and HPRL”, September 2017.
  • [Pronyaev2013] V.G. Pronyaev, A.D. Carlson and R. Capote Noy, “Toward a New Evaluation of Neutron Standards”, IAEA Technical Meeting, 8-12 July 2013, INDC(NDS)-0641.

Review comment:

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

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

Theory/Evaluation

Additional file attached:Simakov2017.pdf
Additional file attached:



Request ID76 Type of the request Special Purpose Quantity
TargetReaction and processIncident EnergySecondary energy or angleTarget uncertaintyCovariance
 26-FE-54 (n,2n) SIG,SPA  252Cf(sf)-235U(n,f)  5-10 Y
FieldSubfieldDate Request createdDate Request acceptedOngoing action
 Dosimetry High-energy 06-OCT-17 06-OCT-17 

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

Project (context): IRDFF project

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

Accuracy:
5%-10%

Justification document:
Accurate cross sections as well as spectrum-averaged cross sections (SACS) in relevant and well-characterized neutron fields are essential for improvement and validation of the evaluated data [Simakov2017].
Following a recommendation from the IAEA Data Development Project on Neutron Standards [Pronyaev2013], the IRDFF project supports SACS measurements of high-threshold (above 10 MeV) dosimetry cross-sections in well-characterized 252Cf(sf) and 235U(nth,f) neutron fields in order to improve the cross sections and/or the high-energy part of the prompt fission neutron spectra.

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

References

  • [IAEA2017] IAEA CRP on Testing and Improving the International Reactor Dosimetry and Fusion File (IRDFF),
    http://www-nds.iaea.org/IRDFFtest/.
  • [Simakov2017] S. Simakov, et al., “Proposals for new measurements for IRDFF community and HPRL”, September 2017.
  • [Pronyaev2013] V.G. Pronyaev, A.D. Carlson and R. Capote Noy, “Toward a New Evaluation of Neutron Standards”, IAEA Technical Meeting, 8-12 July 2013, INDC(NDS)-0641.

Review comment:

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

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

Theory/Evaluation

Additional file attached:Simakov2017.pdf
Additional file attached:Cf252U235_HighThreshold.pdf



Request ID77 Type of the request Special Purpose Quantity
TargetReaction and processIncident EnergySecondary energy or angleTarget uncertaintyCovariance
 69-TM-169 (n,3n) SIG,SPA  252Cf(sf)-235U(n,f)  5-10 Y
FieldSubfieldDate Request createdDate Request acceptedOngoing action
 Dosimetry High-energy 06-OCT-17 06-OCT-17 

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

Project (context): IRDFF project

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

Accuracy:
5%-10%

Justification document:
Accurate cross sections as well as spectrum-averaged cross sections (SACS) in relevant and well-characterized neutron fields are essential for improvement and validation of the evaluated data [Simakov2017].
Following a recommendation from the IAEA Data Development Project on Neutron Standards [Pronyaev2013], the IRDFF project supports SACS measurements of high-threshold (above 10 MeV) dosimetry cross-sections in well-characterized 252Cf(sf) and 235U(nth,f) neutron fields in order to improve the cross sections and/or the high-energy part of the prompt fission neutron spectra.

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

References

  • [IAEA2017] IAEA CRP on Testing and Improving the International Reactor Dosimetry and Fusion File (IRDFF),
    http://www-nds.iaea.org/IRDFFtest/.
  • [Simakov2017] S. Simakov, et al., “Proposals for new measurements for IRDFF community and HPRL”, September 2017.
  • [Pronyaev2013] V.G. Pronyaev, A.D. Carlson and R. Capote Noy, “Toward a New Evaluation of Neutron Standards”, IAEA Technical Meeting, 8-12 July 2013, INDC(NDS)-0641.

Review comment:

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

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

Theory/Evaluation

Additional file attached:Simakov2017.pdf
Additional file attached:Cf252U235_HighThreshold.pdf



Request ID78 Type of the request Special Purpose Quantity
TargetReaction and processIncident EnergySecondary energy or angleTarget uncertaintyCovariance
 83-BI-209 (n,3n) SIG,SPA  252Cf(sf)-235U(n,f)  5-10 Y
FieldSubfieldDate Request createdDate Request acceptedOngoing action
 Dosimetry High-energy 06-OCT-17 06-OCT-17 

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

Project (context): IRDFF project

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

Accuracy:
5%-10%

Justification document:
Accurate cross sections as well as spectrum-averaged cross sections (SACS) in relevant and well-characterized neutron fields are essential for improvement and validation of the evaluated data [Simakov2017].
Following a recommendation from the IAEA Data Development Project on Neutron Standards [Pronyaev2013], the IRDFF project supports SACS measurements of high-threshold (above 10 MeV) dosimetry cross-sections in well-characterized 252Cf(sf) and 235U(nth,f) neutron fields in order to improve the cross sections and/or the high-energy part of the prompt fission neutron spectra.

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

References

  • [IAEA2017] IAEA CRP on Testing and Improving the International Reactor Dosimetry and Fusion File (IRDFF),
    http://www-nds.iaea.org/IRDFFtest/.
  • [Simakov2017] S. Simakov, et al., “Proposals for new measurements for IRDFF community and HPRL”, September 2017.
  • [Pronyaev2013] V.G. Pronyaev, A.D. Carlson and R. Capote Noy, “Toward a New Evaluation of Neutron Standards”, IAEA Technical Meeting, 8-12 July 2013, INDC(NDS)-0641.

Review comment:

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

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

Experiments

Theory/Evaluation

Additional file attached:Simakov2017.pdf
Additional file attached:Cf252U235_HighThreshold.pdf



Request ID79 Type of the request Special Purpose Quantity
TargetReaction and processIncident EnergySecondary energy or angleTarget uncertaintyCovariance
 27-CO-59 (n,3n) SIG,SPA  252Cf(sf)-235U(n,f)  5-10 Y
FieldSubfieldDate Request createdDate Request acceptedOngoing action
 Dosimetry High-energy 06-OCT-17 06-OCT-17 

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

Project (context): IRDFF project

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

Accuracy:
5%-10%

Justification document:
Accurate cross sections as well as spectrum-averaged cross sections (SACS) in relevant and well-characterized neutron fields are essential for improvement and validation of the evaluated data [Simakov2017].
Following a recommendation from the IAEA Data Development Project on Neutron Standards [Pronyaev2013], the IRDFF project supports SACS measurements of high-threshold (above 10 MeV) dosimetry cross-sections in well-characterized 252Cf(sf) and 235U(nth,f) neutron fields in order to improve the cross sections and/or the high-energy part of the prompt fission neutron spectra.

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

References

  • [IAEA2017] IAEA CRP on Testing and Improving the International Reactor Dosimetry and Fusion File (IRDFF),
    http://www-nds.iaea.org/IRDFFtest/.
  • [Simakov2017] S. Simakov, et al., “Proposals for new measurements for IRDFF community and HPRL”, September 2017.
  • [Pronyaev2013] V.G. Pronyaev, A.D. Carlson and R. Capote Noy, “Toward a New Evaluation of Neutron Standards”, IAEA Technical Meeting, 8-12 July 2013, INDC(NDS)-0641.

Review comment:

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

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

Theory/Evaluation

Additional file attached:Simakov2017.pdf
Additional file attached:Cf252U235_HighThreshold.pdf



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

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

Project (context): IRDFF project

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

Accuracy:
2%-5%

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

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

References

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

Review comment:

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

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

Validation

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



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

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

Project (context): IRDFF project

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

Accuracy:
5%-10%

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

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

References

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

Review comment:

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

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

Experiments

Theory/Evaluation

Additional file attached:Simakov2017.pdf
Additional file attached:



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

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

Project (context): IRDFF project

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

Accuracy:
5%-10%

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

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

References

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

Review comment:

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

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

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



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

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

Project (context): IRDFF project

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

Accuracy:
5%-10%

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

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

References

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

Review comment:

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

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

Experiments

Theory/Evaluation

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



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

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

Project (context): IRDFF project

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

Accuracy:
5%-10%

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

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

References

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

Review comment:

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

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

Theory/Evaluation

Additional file attached:Simakov2017.pdf
Additional file attached:



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

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

Project (context): IRDFF project

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

Accuracy:
5%-10%

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

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

References

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

Review comment:

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

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

Theory/Evaluation

Additional file attached:Simakov2017.pdf
Additional file attached:



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

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

Project (context): IRDFF project

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

Accuracy:
5%-10%

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

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

References

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

Review comment:

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

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

Theory/Evaluation

Additional file attached:Simakov2017.pdf
Additional file attached:



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

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

Project (context): IRDFF project

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

Accuracy:
5%-10%

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

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

References

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

Review comment:

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

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

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



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

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

Project (context): IRDFF project

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

Accuracy:
5%-10%

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

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

References

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

Review comment:

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

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

Experiments

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

Theory/Evaluation

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



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

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

Project (context): IRDFF project

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

Accuracy:
5%-10%

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

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

References

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

Review comment:

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

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

Theory/Evaluation

Additional file attached:Simakov2017.pdf
Additional file attached:



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

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

Project (context): IRDFF project

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

Accuracy:
5%-10%

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

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

References

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

Review comment:

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

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

Experiments

Theory/Evaluation

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



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

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

Project (context): IRDFF project

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

Accuracy:
5%-10%

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

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

References

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

Review comment:

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

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

Experiments

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



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

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

Project (context): IRDFF project

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

Accuracy:
5%-10%

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

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

References

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

Review comment:

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

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

Experiments

Theory/Evaluation

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



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

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

Project (context): IRDFF project

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

Accuracy:
5%-10%

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

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

References

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

Review comment:

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

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

Experiments

Theory/Evaluation

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



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

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

Project (context): IRDFF project

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

Accuracy:
5%-10%

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

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

References

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

Review comment:

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

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

Experiments

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

Theory/Evaluation

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



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

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

Project (context): IRDFF project

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

Accuracy:
5%-10%

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

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

References

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

Review comment:

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

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

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



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

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

Project (context): IRDFF project

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

Accuracy:
5%-10%

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

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

References

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

Review comment:

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

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

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



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

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

Project (context):

Impact:

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

Accuracy:

5% of the cross-section

Justification document:

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

References

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

Comment from requester:

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

Review comment:

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

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

Experiments

  • U-235 measurement performed at n_TOF in 2018

Theory/Evaluation

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

Additional file attached:
Additional file attached:



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

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

Project (context):

Impact:

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

Accuracy:

5% of the cross-section

Justification document:

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

References

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

Comment from requester:

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

Review comment:

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

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

Theory/Evaluation

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

Additional file attached:
Additional file attached:



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

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

Project (context):

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

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

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

References

  1. D. Brown, et al., ENDF/B-VIII.0: The 8th Major Release of the Nuclear Reaction Data Library with CIELO-project Cross Sections, New Standards and Thermal Scattering Data, Nuclear Data Sheets 148 (2018) 1 (http://doi.org/10.1016/j.nds.2018.02.001)
  2. R. Capote et al., Prompt Fission Neutron Spectra of Actinides, Nuclear Data Sheets 131 (2016) 1 (http://doi.org/10.1016/j.nds.2015.12.002)

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

Review comment:

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

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

Additional file attached:
Additional file attached:



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

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

Project (context):

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

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

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

References

  1. D. Brown, et al., ENDF/B-VIII.0: The 8th Major Release of the Nuclear Reaction Data Library with CIELO-project Cross Sections, New Standards and Thermal Scattering Data, Nuclear Data Sheets 148 (2018) 1 (http://doi.org/10.1016/j.nds.2018.02.001)
  2. R. Capote et al., Prompt Fission Neutron Spectra of Actinides, Nuclear Data Sheets 131 (2016) 1 (http://doi.org/10.1016/j.nds.2015.12.002)

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

Review comment:

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

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

Additional file attached:
Additional file attached:



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

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

Project (context):

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

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

Justification document:
No SACS measurements exist in Pu-239(nth,f) prompt neutron field. In the latest IAEA evaluation, the extrapolation of Pu-239(nth,f) PFNS to outgoing energies above 8 MeV is based on SACS estimated by interpolation between SACS measured in U-233, U-235 and Cf-252 prompt neutron