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
—