Monte Carlo solver for UWB1 nuclear fuel depletion code
Identifikátory výsledku
Kód výsledku v 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>
Nalezeny alternativní kódy
RIV/68407700:21220/15:00240646
Výsledek na webu
<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>
Alternativní jazyky
Jazyk výsledku
angličtina
Název v původním jazyce
Monte Carlo solver for UWB1 nuclear fuel depletion code
Popis výsledku v původním jazyce
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
Název v anglickém jazyce
Monte Carlo solver for UWB1 nuclear fuel depletion code
Popis výsledku anglicky
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
Klasifikace
Druh
J<sub>x</sub> - Nezařazeno - Článek v odborném periodiku (Jimp, Jsc a Jost)
CEP obor
JF - Jaderná energetika
OECD FORD obor
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Návaznosti výsledku
Projekt
<a href="/cs/project/TE01020455" target="_blank" >TE01020455: Centrum pokročilých jaderných technologií (CANUT)</a><br>
Návaznosti
P - Projekt vyzkumu a vyvoje financovany z verejnych zdroju (s odkazem do CEP)
Ostatní
Rok uplatnění
2015
Kód důvěrnosti údajů
S - Úplné a pravdivé údaje o projektu nepodléhají ochraně podle zvláštních právních předpisů
Údaje specifické pro druh výsledku
Název periodika
Annals of nuclear energy
ISSN
0306-4549
e-ISSN
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Svazek periodika
85
Číslo periodika v rámci svazku
85
Stát vydavatele periodika
NL - Nizozemsko
Počet stran výsledku
10
Strana od-do
778-787
Kód UT WoS článku
000361413800084
EID výsledku v databázi Scopus
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