Qualification of Coupled 3-D Neutron-Kinetic/Thermal-Hydraulic Code Systems by the Calculation of Main-Steam-Line-Break Benchmark in an NPP with VVER-440 Reactor

Kód výsledku v IS VaVaI

<a href="https://www.isvavai.cz/riv?ss=detail&h=RIV%2F46356088%3A_____%2F07%3A%230000957" target="_blank" >RIV/46356088:_____/07:#0000957 - isvavai.cz</a>

Výsledek na webu

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DOI - Digital Object Identifier

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Jazyk výsledku

angličtina

Název v původním jazyce

Qualification of Coupled 3-D Neutron-Kinetic/Thermal-Hydraulic Code Systems by the Calculation of Main-Steam-Line-Break Benchmark in an NPP with VVER-440 Reactor

Popis výsledku v původním jazyce

Recently, three-dimensional neutron-kinetics core models have been coupled to advanced thermalhydraulic system codes. These coupled codes can be used for the analysis of the whole reactor system. In the framework of the international association Atomic Energy Research (AER) on VVER Reactor Physics and Reactor Safety, two benchmarks for these code systems were defined. The reference reactor is the Russian VVER-440. The response of the reactor core to a symmetric and an asymmetric main steam line break should be investigated. So, different aspects of the coupling could be tested. As an additional feature, the participants had to use their own nuclear data. Each of these benchmarks was calculated by five different code systems.

Název v anglickém jazyce

Qualification of Coupled 3-D Neutron-Kinetic/Thermal-Hydraulic Code Systems by the Calculation of Main-Steam-Line-Break Benchmark in an NPP with VVER-440 Reactor

Popis výsledku anglicky

Recently, three-dimensional neutron-kinetics core models have been coupled to advanced thermalhydraulic system codes. These coupled codes can be used for the analysis of the whole reactor system. In the framework of the international association Atomic Energy Research (AER) on VVER Reactor Physics and Reactor Safety, two benchmarks for these code systems were defined. The reference reactor is the Russian VVER-440. The response of the reactor core to a symmetric and an asymmetric main steam line break should be investigated. So, different aspects of the coupling could be tested. As an additional feature, the participants had to use their own nuclear data. Each of these benchmarks was calculated by five different code systems.

Druh

J_x - Nezařazeno - Článek v odborném periodiku (Jimp, Jsc a Jost)

CEP obor

JF - Jaderná energetika

OECD FORD obor

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Projekt

<a href="/cs/project/FT-TA4%2F083" target="_blank" >FT-TA4/083: Bezpečnostní a legislativní aspekty výstavby a spouštění JE nové generace pro energetiku ČR.</a><br>

Návaznosti

P - Projekt vyzkumu a vyvoje financovany z verejnych zdroju (s odkazem do CEP)

Rok uplatnění

2007

Kód důvěrnosti údajů

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

Název periodika

Nuclear Science and Engineering

ISSN

0029-5639

e-ISSN

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Svazek periodika

157

Číslo periodika v rámci svazku

3

Stát vydavatele periodika

US - Spojené státy americké

Počet stran výsledku

26

Strana od-do

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Kód UT WoS článku

000250429900003

EID výsledku v databázi Scopus

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