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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

  • Czech description

Classification

  • Type

    D - Article in proceedings

  • CEP classification

  • 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

  • ISSN

    2100-014X

  • e-ISSN

  • Number of pages

    4

  • Pages from-to

    1-4

  • Publisher name

  • Place of publication

  • Event location

    online

  • Event date

    Jul 21, 2022

  • Type of event by nationality

    WRD - Celosvětová akce

  • UT code for WoS article

    001006475600098