MELCOR and ASTEC validation on prelude test
The result's identifiers
Result code in 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>
Result on the web
<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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Alternative languages
Result language
angličtina
Original language name
MELCOR and ASTEC validation on prelude test
Original language description
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).
Czech name
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Czech description
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Classification
Type
D - Article in proceedings
CEP classification
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OECD FORD branch
20305 - Nuclear related engineering; (nuclear physics to be 1.3);
Result continuities
Project
<a href="/en/project/TH02020666" target="_blank" >TH02020666: Advanced Analytical Tools for Severe Accident Simulations</a><br>
Continuities
P - Projekt vyzkumu a vyvoje financovany z verejnych zdroju (s odkazem do CEP)
Others
Publication year
2019
Confidentiality
S - Úplné a pravdivé údaje o projektu nepodléhají ochraně podle zvláštních právních předpisů
Data specific for result type
Article name in the collection
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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Number of pages
14
Pages from-to
6440-6453
Publisher name
American Nuclear Society
Place of publication
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Event location
Portland, USA
Event date
Aug 18, 2019
Type of event by nationality
WRD - Celosvětová akce
UT code for WoS article
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