Influence of cross-section uncertainties on the calculated results from a thermo-hydraulics code
The result's identifiers
Result code in IS VaVaI
<a href="https://www.isvavai.cz/riv?ss=detail&h=RIV%2F68407700%3A21340%2F20%3A00342530" target="_blank" >RIV/68407700:21340/20:00342530 - isvavai.cz</a>
Result on the web
<a href="https://doi.org/10.1016/j.anucene.2020.107598" target="_blank" >https://doi.org/10.1016/j.anucene.2020.107598</a>
DOI - Digital Object Identifier
<a href="http://dx.doi.org/10.1016/j.anucene.2020.107598" target="_blank" >10.1016/j.anucene.2020.107598</a>
Alternative languages
Result language
angličtina
Original language name
Influence of cross-section uncertainties on the calculated results from a thermo-hydraulics code
Original language description
This study deals with the influence of uncertainties in selected cross-section data in a neutronics code while their impact on the results from thermo-hydraulics code is investigated. Particular cross-section data were defined according to the Phenomenon Identification and Ranking Tables (PIRT) for a pressurized water reactor. Uncertainties were identified for the following data: b – delayed neutron fraction precursors and transport, absorption, m-fission, j-fission, down scattering for moderator temperature, moderator density and fuel temperature. As a neutronics code, PARCS in conjunction with thermohydraulics code TRACE was applied. Uncertainty analyses were carried out by the code DAKOTA where coupled PARCS/TRACE calculations were run 146 times in order to meet a two-sided 95/95 confidence interval. In the thermo-hydraulic code thermal power of the reactor core and inner temperature of the fuel rod were studied. This research shows that the most influential parameters associated with crosssection parametrization are moderator temperature and fuel temperature.
Czech name
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Czech description
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Classification
Type
J<sub>imp</sub> - Article in a specialist periodical, which is included in the Web of Science database
CEP classification
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OECD FORD branch
10304 - Nuclear physics
Result continuities
Project
<a href="/en/project/EF16_013%2F0001790" target="_blank" >EF16_013/0001790: Strengthening and development of research at Czech Technical University in Prague with the use of research infrastructure VR?1 Training Reactor for research activities</a><br>
Continuities
P - Projekt vyzkumu a vyvoje financovany z verejnych zdroju (s odkazem do CEP)
Others
Publication year
2020
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
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Volume of the periodical
145
Issue of the periodical within the volume
May
Country of publishing house
GB - UNITED KINGDOM
Number of pages
8
Pages from-to
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UT code for WoS article
000540700300031
EID of the result in the Scopus database
2-s2.0-85085269483