| Request ID | 88 | Type of the request | Special Purpose Quantity | ||
| Target | Reaction and process | Incident Energy | Secondary energy or angle | Target uncertainty | Covariance |
| 41-NB-93 | (n,xn) x=2-4 SIG | 15MeV/Thr.-100 MeV | 5-10 | Y | |
| Field | Subfield | Date Request created | Date Request accepted | Ongoing action | |
| Dosimetry | High-energy | 06-OCT-17 | 06-OCT-17 | ||
Requester: Dr Stanislav SIMAKOV at KARLSRUHE, GER
Email: intersurfen@gmail.com
Project (context): IRDFF project
Impact:
Accuracy:
Justification document:
Comment from requester: References
Review comment:
Entry Status:
Main references: Experiments Theory/Evaluation Additional file attached:Simakov2017.pdf
Requester: Dr Roberto CAPOTE NOY at IAEA, AUT
Project (context):
Impact:
Accuracy:
Justification document: References
Comment from requester:
Review comment:
Entry Status:
Main references:
The International Reactor Dosimetry and Fusion File (IRDFF) aims at providing evaluated neutron dosimetry reactions validated for all applications related to fission reactors and fusion technology development [IAEA2017].
5%-10%
Accurate cross sections as well as spectrum-averaged cross sections (SACS) in relevant and well-characterized neutron fields are essential for improvement and validation of the evaluated data [Simakov2017].
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
http://www-nds.iaea.org/IRDFFtest/.
Work in progress (as of SG-C review of May 2018)
Please report any missing information to hprlinfo@oecd-nea.org
Additional file attached:Nb(n,xn).pdf
Request ID 111
Type of the request Special Purpose Quantity
Target Reaction and process Incident Energy Secondary energy or angle Target uncertainty Covariance
41-NB-93 (n,2n)Nb-92m SIG/SPA 239Pu(n,f) 3 Y
Field Subfield Date Request created Date Request accepted Ongoing action
Fission Dosimetry 26-MAR-18 06-JUN-18
Email: roberto.capotenoy@iaea.org
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].
3% cross-section ratio uncertainty relative to reference cross sections
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].
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).
Work in progress (as of SG-C review of June 2019)
Please report any missing information to hprlinfo@oecd-nea.org