Neutronic analysis for VVER-440 type reactor using PARCS code
Identifikátory výsledku
Kód výsledku v IS VaVaI
<a href="https://www.isvavai.cz/riv?ss=detail&h=RIV%2F86652052%3A_____%2F18%3AN0000043" target="_blank" >RIV/86652052:_____/18:N0000043 - isvavai.cz</a>
Výsledek na webu
<a href="http://dx.doi.org/10.1115/ICONE26-82607" target="_blank" >http://dx.doi.org/10.1115/ICONE26-82607</a>
DOI - Digital Object Identifier
<a href="http://dx.doi.org/10.1115/ICONE26-82607" target="_blank" >10.1115/ICONE26-82607</a>
Alternativní jazyky
Jazyk výsledku
angličtina
Název v původním jazyce
Neutronic analysis for VVER-440 type reactor using PARCS code
Popis výsledku v původním jazyce
The Czech Republic National Radiation Protection Institute (SURO) provides technical support to the Czech Republic State Office for Nuclear Safety, providing safety analysis and reviewing of the technical documentations for Nuclear Power Plants (NPPs). For this reason, several computational models created in SURO were prepared using different codes as tools to simulate and investigate the design base and beyond design base accidents scenarios.This paper focuses on the creation of SCALE and PARCS neutronic models for a proper analysis of the VVER-440 reactor analysis. In particular, SCALE models of the VVER-440 fuel assemblies have been created in order to produce collapsed and homogenized cross sections necessary for the study with PARCS of the whole VVER-440 reactor core.The sensitivity study of the suitable energy threshold to be adopted for the preparation with SCALE of collapsed two energy-group homogenized cross sections is also discussed. Finally, the results obtained with PARCS core model are compared with those reported in the VVER-440 Final Safety Report.
Název v anglickém jazyce
Neutronic analysis for VVER-440 type reactor using PARCS code
Popis výsledku anglicky
The Czech Republic National Radiation Protection Institute (SURO) provides technical support to the Czech Republic State Office for Nuclear Safety, providing safety analysis and reviewing of the technical documentations for Nuclear Power Plants (NPPs). For this reason, several computational models created in SURO were prepared using different codes as tools to simulate and investigate the design base and beyond design base accidents scenarios.This paper focuses on the creation of SCALE and PARCS neutronic models for a proper analysis of the VVER-440 reactor analysis. In particular, SCALE models of the VVER-440 fuel assemblies have been created in order to produce collapsed and homogenized cross sections necessary for the study with PARCS of the whole VVER-440 reactor core.The sensitivity study of the suitable energy threshold to be adopted for the preparation with SCALE of collapsed two energy-group homogenized cross sections is also discussed. Finally, the results obtained with PARCS core model are compared with those reported in the VVER-440 Final Safety Report.
Klasifikace
Druh
D - Stať ve sborníku
CEP obor
—
OECD FORD obor
10304 - Nuclear physics
Návaznosti výsledku
Projekt
—
Návaznosti
I - Institucionalni podpora na dlouhodoby koncepcni rozvoj vyzkumne organizace
Ostatní
Rok uplatnění
2018
Kód důvěrnosti údajů
S - Úplné a pravdivé údaje o projektu nepodléhají ochraně podle zvláštních právních předpisů
Údaje specifické pro druh výsledku
Název statě ve sborníku
PROCEEDINGS OF THE 26TH INTERNATIONAL CONFERENCE ON NUCLEAR ENGINEERING
ISBN
978-0-7918-5153-1
ISSN
—
e-ISSN
—
Počet stran výsledku
10
Strana od-do
1-10
Název nakladatele
ASME
Místo vydání
London
Místo konání akce
London
Datum konání akce
22. 7. 2018
Typ akce podle státní příslušnosti
WRD - Celosvětová akce
Kód UT WoS článku
000461413200096