Spectral averaged cross sections as a probe to a high energy tail of U-235 PFNS
The result's identifiers
Result code in IS VaVaI
<a href="https://www.isvavai.cz/riv?ss=detail&h=RIV%2F26722445%3A_____%2F23%3AN0000048" target="_blank" >RIV/26722445:_____/23:N0000048 - isvavai.cz</a>
Result on the web
<a href="https://www.epj-conferences.org/articles/epjconf/abs/2023/10/epjconf_nd2023_04021/epjconf_nd2023_04021.html" target="_blank" >https://www.epj-conferences.org/articles/epjconf/abs/2023/10/epjconf_nd2023_04021/epjconf_nd2023_04021.html</a>
DOI - Digital Object Identifier
<a href="http://dx.doi.org/10.1051/epjconf/202328404021" target="_blank" >10.1051/epjconf/202328404021</a>
Alternative languages
Result language
angličtina
Original language name
Spectral averaged cross sections as a probe to a high energy tail of U-235 PFNS
Original language description
The systematic evaluations of spectrum averaged cross sections of dosimetric reactions over a broad range of energies were performed in Cf-252 (spontaneous fission) and U-235(nth,f) neutron fields. The neutron sources used in this study were LR-0, VR-1 zero power research light water reactors, LVR-15 10 MW research light water reactor, and Cf-252 neutron source with emission specified precisely by the manganese sulphate bath. All spectral averaged cross sections were inferred from measured reaction rates which were derived from gamma spectrometry. These gamma spectrometry measurements were performed using a single detector in all cases. The ratios of Cf-252 and U-235 spectral averaged cross sections can be used to specify the high energy tail of the U-235 prompt fission neutron spectrum as the Cf-252 spontaneous fission spectrum is considered as a standard. Furthermore, ratios are independent of cross section uncertainties since uncertainties in the cross sections are eliminated. Theoretical models of fission can be tested based on our measurements. The calculations were performed in MCNP6.2 transport code using different prompt fission neutron spectra and IRDFF-II cross sections for threshold reactions. The ratios are in good agreement using only ENDF/B-VIII.0 235U prompt fission neutron spectrum suggesting it to be harder than in other evaluations.
Czech name
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Czech description
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Classification
Type
D - Article in proceedings
CEP classification
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OECD FORD branch
10303 - Particles and field physics
Result continuities
Project
<a href="/en/project/LM2023041" target="_blank" >LM2023041: Czech International Centre of Research Reactors</a><br>
Continuities
P - Projekt vyzkumu a vyvoje financovany z verejnych zdroju (s odkazem do CEP)
Others
Publication year
2023
Confidentiality
S - Úplné a pravdivé údaje o projektu nepodléhají ochraně podle zvláštních právních předpisů
Data specific for result type
Article name in the collection
15TH INTERNATIONAL CONFERENCE ON NUCLEAR DATA FOR SCIENCE AND TECHNOLOGY, ND2022
ISBN
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ISSN
2100-014X
e-ISSN
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Number of pages
4
Pages from-to
1-4
Publisher name
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Place of publication
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Event location
online
Event date
Jul 21, 2022
Type of event by nationality
WRD - Celosvětová akce
UT code for WoS article
001006475600098