50-Sn-117(n,inl)Sn-117m
ID |
80
|
Type |
|
Target |
50-Sn-117
|
Reaction |
(n,inl)Sn-117m
|
Quantity |
SIG - Cross section
|
Incident energy |
5 MeV - 10 MeV
|
Accuracy |
2-5 %
|
Field(s) |
Dosimetry
|
Subfield |
Fast fission, D-T fusion
|
Accepted date |
06-Oct-2017
|
Status |
Work in progress
|
Latest review date |
22-Apr-2022
|
Requester
Mr Christophe DESTOUCHES at CAD-DER, 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).
Entry status
Work in progress (as of SG-C review of May 2018)
Main recent references
Please report any missing information to hprlinfo@oecd-nea.org
Validation
- S. Bourganel, et al., Analysis of the FLUOLE-2 program: UOX/MOX core loading configurations, 16th International Symposium on Reactor Dosimetry, May 7-12, 2017, Santa Fe (NM), USA, ASTM International, 2018, STP1608, pp. 296-307
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