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The effect of local power increase on neutron flux in internal parts of the VVER-1000 Mock-Up in LR-0 reactor

The result's identifiers

  • Result code in IS VaVaI

    <a href="https://www.isvavai.cz/riv?ss=detail&h=RIV%2F26722445%3A_____%2F18%3AN0000027" target="_blank" >RIV/26722445:_____/18:N0000027 - isvavai.cz</a>

  • Alternative codes found

    RIV/60162694:G43__/18:00536175 RIV/00216224:14330/18:00103750

  • Result on the web

    <a href="http://dx.doi.org/10.1016/j.anucene.2018.08.007" target="_blank" >http://dx.doi.org/10.1016/j.anucene.2018.08.007</a>

  • DOI - Digital Object Identifier

    <a href="http://dx.doi.org/10.1016/j.anucene.2018.08.007" target="_blank" >10.1016/j.anucene.2018.08.007</a>

Alternative languages

  • Result language

    angličtina

  • Original language name

    The effect of local power increase on neutron flux in internal parts of the VVER-1000 Mock-Up in LR-0 reactor

  • Original language description

    The neutron flux distribution in the internal parts of a reactor is an important parameter which affects the absorbed dose, temperature, and gas production in the materials. Therefore, the knowledge of neutron flux distribution, for example in the baffle, is important for estimation of the radiation-induced swelling and activation of this internal component. The power distribution in the periphery fuel assemblies, mostly the lateral 2-3 pin rows, has considerable influence on neutron and gamma flux in the internal reactor elements. The power distribution in the core is mostly calculated by the reactor operator using diffusion codes. These data are used as an input for transport calculations, e.g., with Monte Carlo for the fluences, displacements per atoms, gamma heating and other important values for radiation damage estimation. This paper aims to compare the experimental and calculated reaction rate distribution in a mock-up of VVER-1000 (VVER-1000 Mock-Up) internals placed in the LR-0 reactor and compares these quantities in case of a partial change of enrichment in one fuel assembly adjacent to the baffle simulator.

  • 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

    2018

  • Confidentiality

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

Data specific for result type

  • Name of the periodical

    Annals of Nuclear Energy

  • ISSN

    0306-4549

  • e-ISSN

  • Volume of the periodical

    121

  • Issue of the periodical within the volume

    November

  • Country of publishing house

    GB - UNITED KINGDOM

  • Number of pages

    10

  • Pages from-to

    567-576

  • UT code for WoS article

    000444668200054

  • EID of the result in the Scopus database

    2-s2.0-85051408685