Experimental Analyses of Phebus facility using MELCOR code version 2.2

Result code in IS VaVaI

<a href="https://www.isvavai.cz/riv?ss=detail&h=RIV%2F26722445%3A_____%2F20%3AN0000169" target="_blank" >RIV/26722445:_____/20:N0000169 - isvavai.cz</a>

Result on the web

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DOI - Digital Object Identifier

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Result language

angličtina

Original language name

Experimental Analyses of Phebus facility using MELCOR code version 2.2

Original language description

The activity focuses on developing the PHEBUS FPT-3 facility model for assessing the capabilities of the MELCOR code version 2.2, in simulating the degradation phenomena during a SA from the ThermoHydraulic behaviour up to the fission products release in the reactor coolant system and the containment building, which should be occurred in VVER technology during a Severe Accident. Particular attention is given to the Boron Carbide oxidation simplify model and how it influences of core melt progression and the release model. In addition, the FP transport was modelled focusing on the releases and transport as it used to be simulated in MELCOR. For this reason, two different nodalizations were prepared in order to understand the influence of the release model on the source term in the containment vessel. One nodalization is characterized by a complete model of the facility from the active channel (fuel bundle) up to the containment vessel. For the second nodalization, the active channel (fuel bundle) was removed and simulating the circuit from the steam generator to the containment vessel. For this nodalization the steam, hydrogen and FPs are imposed as boundary condition from the data obtained by the experiment in the Point C (hot leg). In addition, those two nodalizations are modelling and simulating in two different versions of the MELCOR code (2.1 and 2.2): this benchmark code-to-code is used as additional assessment for the MELCOR 2.2 code in parallel with the comparison of the results with the PHEBUS experiment. Report CVŘ-3660

Czech name

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Czech description

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Type

O - Miscellaneous

CEP classification

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OECD FORD branch

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

Project

<a href="/en/project/VI20172020076" target="_blank" >VI20172020076: More accurate prediction of radiological consequences of severe accidents at NPP aimed in identification of their risks</a><br>

Continuities

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

Publication year

2020

Confidentiality

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