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Influence of cross-section uncertainties on the calculated results from a thermo-hydraulics code

The result's identifiers

  • Result code in IS VaVaI

    <a href="https://www.isvavai.cz/riv?ss=detail&h=RIV%2F68407700%3A21340%2F20%3A00342530" target="_blank" >RIV/68407700:21340/20:00342530 - isvavai.cz</a>

  • Result on the web

    <a href="https://doi.org/10.1016/j.anucene.2020.107598" target="_blank" >https://doi.org/10.1016/j.anucene.2020.107598</a>

  • DOI - Digital Object Identifier

    <a href="http://dx.doi.org/10.1016/j.anucene.2020.107598" target="_blank" >10.1016/j.anucene.2020.107598</a>

Alternative languages

  • Result language

    angličtina

  • Original language name

    Influence of cross-section uncertainties on the calculated results from a thermo-hydraulics code

  • Original language description

    This study deals with the influence of uncertainties in selected cross-section data in a neutronics code while their impact on the results from thermo-hydraulics code is investigated. Particular cross-section data were defined according to the Phenomenon Identification and Ranking Tables (PIRT) for a pressurized water reactor. Uncertainties were identified for the following data: b – delayed neutron fraction precursors and transport, absorption, m-fission, j-fission, down scattering for moderator temperature, moderator density and fuel temperature. As a neutronics code, PARCS in conjunction with thermohydraulics code TRACE was applied. Uncertainty analyses were carried out by the code DAKOTA where coupled PARCS/TRACE calculations were run 146 times in order to meet a two-sided 95/95 confidence interval. In the thermo-hydraulic code thermal power of the reactor core and inner temperature of the fuel rod were studied. This research shows that the most influential parameters associated with crosssection parametrization are moderator temperature and fuel temperature.

  • 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

    10304 - Nuclear physics

Result continuities

  • Project

    <a href="/en/project/EF16_013%2F0001790" target="_blank" >EF16_013/0001790: Strengthening and development of research at Czech Technical University in Prague with the use of research infrastructure VR?1 Training Reactor for research activities</a><br>

  • Continuities

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

Others

  • Publication year

    2020

  • 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

    145

  • Issue of the periodical within the volume

    May

  • Country of publishing house

    GB - UNITED KINGDOM

  • Number of pages

    8

  • Pages from-to

  • UT code for WoS article

    000540700300031

  • EID of the result in the Scopus database

    2-s2.0-85085269483