VALIDATION STUDY OF FUEL ASSEMBLY MODEL OF VVER 1000 REACTOR BY TRITON

Kód výsledku v IS VaVaI

<a href="https://www.isvavai.cz/riv?ss=detail&h=RIV%2F00216305%3A26220%2F18%3APU128313" target="_blank" >RIV/00216305:26220/18:PU128313 - 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

VALIDATION STUDY OF FUEL ASSEMBLY MODEL OF VVER 1000 REACTOR BY TRITON

Popis výsledku v původním jazyce

This paper describes the fuel assembly model of VVER 1000 reactor. This model was developed based on document In-core fuel management code package validation for WWERs. The fuel assembly of Kalinin Unit 1 is described in document. The fuel assembly model has been created by reactor physics analysis tool TRITON (Code package Scale 6.2). The fuel assembly model has been validated by the results of benchmark participation and model of Monte Carlo code Keno. Several cases with different fuel, moderator and cladding temperature, enrichment, boron concentration in moderator were calculated. The depletation calculation has been also computed. The newest cross section library ENDF/B-VI. 252 neutron groups has been used for calculation. The impact of used cross section libraries to results has been discussed in this paper. The model of fuel assembly in TRITON will be used for generating macroscopic cross section library for further simulation in nodal code PARCS. Coupled calculation of nodal code and thermal hydraulic code is necessary for safety analyses with nonsymmetrical power distribution in the core. This report describe the results of second part of knowledge transfer project between Brno University of Technology and company TES. This report will support certification of computation tool for safety analyses.

Název v anglickém jazyce

VALIDATION STUDY OF FUEL ASSEMBLY MODEL OF VVER 1000 REACTOR BY TRITON

Popis výsledku anglicky

This paper describes the fuel assembly model of VVER 1000 reactor. This model was developed based on document In-core fuel management code package validation for WWERs. The fuel assembly of Kalinin Unit 1 is described in document. The fuel assembly model has been created by reactor physics analysis tool TRITON (Code package Scale 6.2). The fuel assembly model has been validated by the results of benchmark participation and model of Monte Carlo code Keno. Several cases with different fuel, moderator and cladding temperature, enrichment, boron concentration in moderator were calculated. The depletation calculation has been also computed. The newest cross section library ENDF/B-VI. 252 neutron groups has been used for calculation. The impact of used cross section libraries to results has been discussed in this paper. The model of fuel assembly in TRITON will be used for generating macroscopic cross section library for further simulation in nodal code PARCS. Coupled calculation of nodal code and thermal hydraulic code is necessary for safety analyses with nonsymmetrical power distribution in the core. This report describe the results of second part of knowledge transfer project between Brno University of Technology and company TES. This report will support certification of computation tool for safety analyses.

Druh

D - Stať ve sborníku

CEP obor

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OECD FORD obor

20305 - Nuclear related engineering; (nuclear physics to be 1.3);

Projekt

<a href="/cs/project/TE01020455" target="_blank" >TE01020455: Centrum pokročilých jaderných technologií (CANUT)</a><br>

Návaznosti

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

Rok uplatnění

2018

Kód důvěrnosti údajů

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

Název statě ve sborníku

PHYSOR 2018: Reactor Physics Paving the Way Towards More Efficient Systems

ISBN

9781713808510

ISSN

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e-ISSN

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Počet stran výsledku

9

Strana od-do

1377-1385

Název nakladatele

Sociedad Nuclear Mexicana, A.C.

Místo vydání

Cancun

Místo konání akce

Cancun

Datum konání akce

22. 4. 2018

Typ akce podle státní příslušnosti

WRD - Celosvětová akce

Kód UT WoS článku

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