Comparison between SERPENT and MONTEBURNS codes applied to burnup calculations of a GFR-like configuration

Result code in IS VaVaI

<a href="https://www.isvavai.cz/riv?ss=detail&h=RIV%2F26722445%3A_____%2F14%3A%230000949" target="_blank" >RIV/26722445:_____/14:#0000949 - isvavai.cz</a>

Result on the web

<a href="http://dx.doi.org/10.1016/j.nucengdes.2014.03.035" target="_blank" >http://dx.doi.org/10.1016/j.nucengdes.2014.03.035</a>

DOI - Digital Object Identifier

<a href="http://dx.doi.org/10.1016/j.nucengdes.2014.03.035" target="_blank" >10.1016/j.nucengdes.2014.03.035</a>

Result language

angličtina

Original language name

Comparison between SERPENT and MONTEBURNS codes applied to burnup calculations of a GFR-like configuration

Original language description

This paper presents the comparison between two Monte Carlo based burnup codes: SERPENT and MONTEBURNS. Monte Carlo codes are fully and worldwide adopted to perform analyses on nuclear facilities, also in the frame of Generation IV advanced reactors simulations. Thus, faster and most powerful calculation codes are needed with the aim to analyze complex geometries and specific neutronic behaviors. Burnup calculations are an efficient tool to test neutronic Monte Carlo codes: indeed these calculations couple transport and depletion procedures, so that neutronic reactor behavior can be simulated in its totality. Comparisons have been performed on a configuration representing the Allegro MOX 75 MWth reactor proposed by the European GoFastR (Gas-cooled FastReactor) Project in the frame of the 7th Euratom Framework Program. Although in burnup and criticality comparisons the codes used in simulations show different calculation times and some differences in amounts and in precision (in term of

Czech name

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Czech description

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Type

J_x - Unclassified - Peer-reviewed scientific article (Jimp, Jsc and Jost)

CEP classification

JF - Nuclear energy

OECD FORD branch

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Project

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Continuities

V - Vyzkumna aktivita podporovana z jinych verejnych zdroju

Publication year

2014

Confidentiality

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

Name of the periodical

Nuclear Engineering and Design

ISSN

0029-5493

e-ISSN

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Volume of the periodical

273

Issue of the periodical within the volume

7

Country of publishing house

CH - SWITZERLAND

Number of pages

3

Pages from-to

542-554

UT code for WoS article

000337856500049

EID of the result in the Scopus database

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