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Measurement of the selected spectral averaged cross sections in a radial channel of the VR-1 reactor

The result's identifiers

  • Result code in IS VaVaI

    <a href="https://www.isvavai.cz/riv?ss=detail&h=RIV%2F26722445%3A_____%2F19%3AN0000043" target="_blank" >RIV/26722445:_____/19:N0000043 - isvavai.cz</a>

  • Alternative codes found

    RIV/68407700:21340/19:00332404

  • Result on the web

    <a href="https://www.sciencedirect.com/science/article/abs/pii/S0969804319306396" target="_blank" >https://www.sciencedirect.com/science/article/abs/pii/S0969804319306396</a>

  • DOI - Digital Object Identifier

    <a href="http://dx.doi.org/10.1016/j.apradiso.2019.108855" target="_blank" >10.1016/j.apradiso.2019.108855</a>

Alternative languages

  • Result language

    angličtina

  • Original language name

    Measurement of the selected spectral averaged cross sections in a radial channel of the VR-1 reactor

  • Original language description

    The spectral averaged cross section is an important quantity used in a validation of nuclear cross section. When the cross sections are averaged over the neutron standard field (Cf-252(s,f) or U-235(n,f) neutron spectrum), they can be used for tuning of evaluations. This kind of quantities is very useful because the data in integral measurements can be determined with a significantly smaller uncertainties than the standard differential data. The experiment was aimed at the spectral average cross sections measurement and was performed in a radial channel of VR-1 reactor (with fuel enrichment 19.75 wt %). The results are in a good agreement within the uncertainties with a previous measurements in LR-0 reactor (with fuel enrichment 3.3 wt %), thus it supports the hypothesis that even significant amount of U-238(n,f) neutrons in the LR-0 reactor spectrum does not have a significant influence. The derived spectral averaged cross sections are as follows: 0.1709 +/- 0.0115 mb for Y-89(n,2n), 10.738 +/- 0.719 mb for Ti-46(n,p), 17.896 +/- 1.181 mb for Ti-47(n,p), 0.294 +/- 0.02 mb for Ti-48(n,p), 72.994 +/- 4.964 mb for Fe-54(n,p), 0.528 +/- 0.036 mb for Cu-63(n,a), 0.444 +/- 0.029 mb for Nb-93(n,2n)Nb-92* and 0.239 +/- 0.016 mb for Ni-58(n,x)Co-57.

  • Czech name

  • Czech description

Classification

  • Type

    J<sub>imp</sub> - Article in a specialist periodical, which is included in the Web of Science database

  • CEP classification

  • OECD FORD branch

    20305 - Nuclear related engineering; (nuclear physics to be 1.3);

Result continuities

  • Project

    Result was created during the realization of more than one project. More information in the Projects tab.

  • Continuities

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

Others

  • Publication year

    2019

  • Confidentiality

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

Data specific for result type

  • Name of the periodical

    Applied Radiation and Isotopes

  • ISSN

    0969-8043

  • e-ISSN

  • Volume of the periodical

    154

  • Issue of the periodical within the volume

    December

  • Country of publishing house

    GB - UNITED KINGDOM

  • Number of pages

    7

  • Pages from-to

    1-7

  • UT code for WoS article

    000498291900009

  • EID of the result in the Scopus database

    2-s2.0-85070815748