MELCOR and ASTEC validation on prelude test

Kód výsledku v IS VaVaI

<a href="https://www.isvavai.cz/riv?ss=detail&h=RIV%2F46356088%3A_____%2F19%3AN0000026" target="_blank" >RIV/46356088:_____/19:N0000026 - isvavai.cz</a>

Výsledek na webu

<a href="http://www.ans.org/store/item-700431/" target="_blank" >http://www.ans.org/store/item-700431/</a>

DOI - Digital Object Identifier

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Jazyk výsledku

angličtina

Název v původním jazyce

MELCOR and ASTEC validation on prelude test

Popis výsledku v původním jazyce

In the past at ÚJV Řež, two integral codes – MELCOR and ASTEC – were assessed for their capabilities of simulating quenching of debris bed. Recently, the current releases of both codes (versions 2.2 and 2.1.1.4, respectively) were used to revisit the numerical study, with the goal of assessing the progress both codes have made in their capabilities of simulating the complex phenomena which occurr when a massively degraded reactor core, being already in the form of a debris bed, is reflooded. The test numbered 126 from the PRELUDE experimental program was selected for this purpose. Concerning the ASTEC code simulation, in the latest version released a new approach for the quenching modeling of a super-heated core is implemented. Thus, the ASTEC simulation results serve both for the cross-walk study between MELCOR and ASTEC and for the assessment of ASTEC model improvements (a brief comparison is made between the previous and recent ASTEC calculations for the PRELUDE-126 experiment).

Název v anglickém jazyce

MELCOR and ASTEC validation on prelude test

Popis výsledku anglicky

In the past at ÚJV Řež, two integral codes – MELCOR and ASTEC – were assessed for their capabilities of simulating quenching of debris bed. Recently, the current releases of both codes (versions 2.2 and 2.1.1.4, respectively) were used to revisit the numerical study, with the goal of assessing the progress both codes have made in their capabilities of simulating the complex phenomena which occurr when a massively degraded reactor core, being already in the form of a debris bed, is reflooded. The test numbered 126 from the PRELUDE experimental program was selected for this purpose. Concerning the ASTEC code simulation, in the latest version released a new approach for the quenching modeling of a super-heated core is implemented. Thus, the ASTEC simulation results serve both for the cross-walk study between MELCOR and ASTEC and for the assessment of ASTEC model improvements (a brief comparison is made between the previous and recent ASTEC calculations for the PRELUDE-126 experiment).

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/TH02020666" target="_blank" >TH02020666: Pokročilé analytické nástroje pro těžké havárie</a><br>

Návaznosti

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

Rok uplatnění

2019

Kód důvěrnosti údajů

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

Název statě ve sborníku

18th International Topical Meeting on Nuclear Reactor Thermal Hydraulics, NURETH 2019 2019

ISBN

978-0-89448-767-5

ISSN

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e-ISSN

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Počet stran výsledku

14

Strana od-do

6440-6453

Název nakladatele

American Nuclear Society

Místo vydání

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Místo konání akce

Portland, USA

Datum konání akce

18. 8. 2019

Typ akce podle státní příslušnosti

WRD - Celosvětová akce

Kód UT WoS článku

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