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Monte Carlo solver for UWB1 nuclear fuel depletion code

The result's identifiers

  • Result code in IS VaVaI

    <a href="https://www.isvavai.cz/riv?ss=detail&h=RIV%2F49777513%3A23220%2F15%3A43925772" target="_blank" >RIV/49777513:23220/15:43925772 - isvavai.cz</a>

  • Alternative codes found

    RIV/68407700:21220/15:00240646

  • Result on the web

    <a href="http://ac.els-cdn.com/S0306454915003497/1-s2.0-S0306454915003497-main.pdf?_tid=82a4533a-52d5-11e5-8769-00000aab0f01&acdnat=1441351447_1fec8252a0e7dfe8ec4e395cfcb39fb9" target="_blank" >http://ac.els-cdn.com/S0306454915003497/1-s2.0-S0306454915003497-main.pdf?_tid=82a4533a-52d5-11e5-8769-00000aab0f01&acdnat=1441351447_1fec8252a0e7dfe8ec4e395cfcb39fb9</a>

  • DOI - Digital Object Identifier

    <a href="http://dx.doi.org/10.1016/j.anucene.2015.06.035" target="_blank" >10.1016/j.anucene.2015.06.035</a>

Alternative languages

  • Result language

    angličtina

  • Original language name

    Monte Carlo solver for UWB1 nuclear fuel depletion code

  • Original language description

    Recent nuclear reactor burnable absorber research tries to introduce new materials in the nuclear fuel. As a part of this effort, a fast computational tool is being developed for the advanced nuclear fuel. The first version of the newly developed UWB1 fast nuclear fuel depletion code significantly reduced calculation time by omitting the solution step for the Boltzmann transport equation. However, estimation of neutron multiplication factor during depletion was not sufficiently calculated. Therefore, atleast one transport calculation for fuel depletion is necessary. This paper presents a new Monte Carlo solver that is implemented into the UWB1 code. The UWB1 Monte Carlo solver calculates neutron multiplication factor and neutron flux in the fuel for collapsed cross sections. Accuracy of the solver is supported by using current nuclear data stored in the ENDF/B-VII.1 library. Speed of the solver is the product of development focusing on minimization of CPU utilization at the expense of

  • Czech name

  • Czech description

Classification

  • Type

    J<sub>x</sub> - Unclassified - Peer-reviewed scientific article (Jimp, Jsc and Jost)

  • CEP classification

    JF - Nuclear energy

  • OECD FORD branch

Result continuities

  • Project

    <a href="/en/project/TE01020455" target="_blank" >TE01020455: Centre for Advanced Nuclear Technologies (CANUT)</a><br>

  • Continuities

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

Others

  • Publication year

    2015

  • 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

    85

  • Issue of the periodical within the volume

    85

  • Country of publishing house

    NL - THE KINGDOM OF THE NETHERLANDS

  • Number of pages

    10

  • Pages from-to

    778-787

  • UT code for WoS article

    000361413800084

  • EID of the result in the Scopus database