Spectral averaged cross sections as a probe to a high energy tail of U-235 PFNS

Kód výsledku v 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>

Výsledek na webu

<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>

Jazyk výsledku

angličtina

Název v původním jazyce

Spectral averaged cross sections as a probe to a high energy tail of U-235 PFNS

Popis výsledku v původním jazyce

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.

Název v anglickém jazyce

Spectral averaged cross sections as a probe to a high energy tail of U-235 PFNS

Popis výsledku anglicky

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.

Druh

D - Stať ve sborníku

CEP obor

—

OECD FORD obor

10303 - Particles and field physics

Projekt

<a href="/cs/project/LM2023041" target="_blank" >LM2023041: České mezinárodní centrum výzkumných reaktorů</a><br>

Návaznosti

P - Projekt vyzkumu a vyvoje financovany z verejnych zdroju (s odkazem do CEP)

Rok uplatnění

2023

Kód důvěrnosti údajů

S - Úplné a pravdivé údaje o projektu nepodléhají ochraně podle zvláštních právních předpisů

Název statě ve sborníku

15TH INTERNATIONAL CONFERENCE ON NUCLEAR DATA FOR SCIENCE AND TECHNOLOGY, ND2022

ISBN

—

ISSN

2100-014X

e-ISSN

—

Počet stran výsledku

4

Strana od-do

1-4

Název nakladatele

—

Místo vydání

—

Místo konání akce

online

Datum konání akce

21. 7. 2022

Typ akce podle státní příslušnosti

WRD - Celosvětová akce

Kód UT WoS článku

001006475600098