Cross Sections Influence on Monte Carlo Based Burnup Codes

Result code in IS VaVaI
<a href="https://www.isvavai.cz/riv?ss=detail&h=RIV%2F26722445%3A_____%2F14%3A%230000992" target="_blank" >RIV/26722445:_____/14:#0000992 - isvavai.cz</a>
Result on the web
<a href="http://dx.doi.org/10.1115/ICONE22-31049" target="_blank" >http://dx.doi.org/10.1115/ICONE22-31049</a>
DOI - Digital Object Identifier
<a href="http://dx.doi.org/10.1115/ICONE22-31049" target="_blank" >10.1115/ICONE22-31049</a>

Result language
angličtina
Original language name
Cross Sections Influence on Monte Carlo Based Burnup Codes
Original language description
This paper reports the results of a comparison among JEFF and ENDF/B datasets when used by SERPENT and MONTEBURNS codes on a GFR-like configuration. Particularly, it shows a comparison between the two Monte Carlo based codes, each one adopting three different cross sections dataset, namely JEFF-3.1, JEFF-3.1.2 and ENDF/B-VII.1. Calculations have been carried out on the Allegro reactor, i.e. an experimental GFR-like facility that should be built in EU as GFR demonstrator. Results concern nuclear parameters as effective multiplication factor and fluxes, as well as the atomic densities for some important nuclides versus burnup.
Czech name
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Czech description
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Project
<a href="/en/project/EE2.3.30.0026" target="_blank" >EE2.3.30.0026: Nuclear safety assessment knowledge basis development</a><br>
Continuities
P - Projekt vyzkumu a vyvoje financovany z verejnych zdroju (s odkazem do CEP)

Publication year
2014
Confidentiality
S - Úplné a pravdivé údaje o projektu nepodléhají ochraně podle zvláštních právních předpisů

Article name in the collection
2014 22nd International Conference on Nuclear Engineering Volume 4
ISBN
978-0-7918-4594-3
ISSN
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e-ISSN
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Number of pages
9
Pages from-to
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Publisher name
ASME
Place of publication
New York, USA
Event location
Praha
Event date
Jan 1, 2014
Type of event by nationality
WRD - Celosvětová akce
UT code for WoS article
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