VALIDATION OF THE ALTHAMC12 SUBCHANNEL CODE
Identifikátory výsledku
Kód výsledku v IS VaVaI
<a href="https://www.isvavai.cz/riv?ss=detail&h=RIV%2F00216305%3A26220%2F21%3APU143030" target="_blank" >RIV/00216305:26220/21:PU143030 - isvavai.cz</a>
Výsledek na webu
<a href="https://www.ans.org/pubs/proceedings/article-49145/" target="_blank" >https://www.ans.org/pubs/proceedings/article-49145/</a>
DOI - Digital Object Identifier
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Alternativní jazyky
Jazyk výsledku
angličtina
Název v původním jazyce
VALIDATION OF THE ALTHAMC12 SUBCHANNEL CODE
Popis výsledku v původním jazyce
One of the tools for safety analysis of light water reactors is the subchannel methodology which is used for evaluation of the limits with regards to departure from nucleate boiling (DNB). This approach utilities subchannel code which has to be validated against experimental data. In this work, the ALTHAMC12 subchannel code is validated against critical heat flux data measured at test section with hexagonal geometry. Validation is performed using the PG-S and OKB correlations of critical heat flux (CHF). The experimental data library is based on public literature sources. The analysis shows that PG-S correlation provides prediction of CHF close to experimental values. The OKB correlation underestimates the CHF and thus provides conservative results for safety analysis.
Název v anglickém jazyce
VALIDATION OF THE ALTHAMC12 SUBCHANNEL CODE
Popis výsledku anglicky
One of the tools for safety analysis of light water reactors is the subchannel methodology which is used for evaluation of the limits with regards to departure from nucleate boiling (DNB). This approach utilities subchannel code which has to be validated against experimental data. In this work, the ALTHAMC12 subchannel code is validated against critical heat flux data measured at test section with hexagonal geometry. Validation is performed using the PG-S and OKB correlations of critical heat flux (CHF). The experimental data library is based on public literature sources. The analysis shows that PG-S correlation provides prediction of CHF close to experimental values. The OKB correlation underestimates the CHF and thus provides conservative results for safety analysis.
Klasifikace
Druh
O - Ostatní výsledky
CEP obor
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OECD FORD obor
20305 - Nuclear related engineering; (nuclear physics to be 1.3);
Návaznosti výsledku
Projekt
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Návaznosti
S - Specificky vyzkum na vysokych skolach
Ostatní
Rok uplatnění
2021
Kód důvěrnosti údajů
S - Úplné a pravdivé údaje o projektu nepodléhají ochraně podle zvláštních právních předpisů