Effect of the in- and ex-vessel dual cooling on the retention of an internally heated melt pool in a hemispherical vessel
Creators
- 1. Korea Atomic Energy Research Inst., Thermal Hydraulic Safety Research, Taejon (Korea, Republic of)
Description
A concept of in-vessel melt retention (IVMR) by in-vessel reflooding and/or reactor cavity flooding has been considered as one of severe accident management strategies and intensive researches to be performed worldwide. This paper provides some results of analytical investigations on the effect of both in- / ex-vessel cooling on the retention of an internally heated molten pool confined in a hemispherical vessel and the related thermal behavior of the vessel wall. For the present analysis, a scale-down reactor vessel for the KSNP reactor design of 1000 MWe (a large dry PWR) is utilized for a reactor vessel. Aluminum oxide melt simulant is also utilized for a real corium pool. An internal power density in the molten pool is determined by a simple scaling analysis that equates the heat flux on the the scale-down vessel wall to that estimated from KSNP. Well-known temperature-dependent boiling heat transfer curves are applied to the in- and ex-vessel cooling boundaries and radiative heat transfer has been only considered in the case of dry in-vessel. MELTPOOL, which is a computational fluid dynamics (CFD) code developed at KAERI, is applied to obtain the time-varying heat flux distribution from a molten pool and the vessel wall temperature distributions with angular positions along the vessel wall. In order to gain further insights on the effectiveness of in- and ex-vessel dual cooling on the in-vessel corium retention, four different boundary conditions has been considered: no water inside the vessel without ex-vessel cooling, water inside the vessel without ex-vessel cooling, no water inside the vessel with ex-vessel cooling, and water inside the vessel with ex-vessel cooling. (authors)
Availability note (English)
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33015165.pdf
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Additional details
Publishing Information
- Imprint Pagination
- [15 p.]
- Report number
- INIS-FR--846
Conference
- Title
- 9. international conference on nuclear engineering
- Dates
- 8-12 Apr 2001
- Place
- Nice, Acropolis (France)
INIS
- Country of Publication
- France
- Country of Input or Organization
- France
- INIS RN
- 33015165
- Subject category
- S22: GENERAL STUDIES OF NUCLEAR REACTORS;
- Resource subtype / Literary indicator
- Conference
- Descriptors DEI
- COMPUTERIZED SIMULATION; CORE CATCHERS; CORIUM; HEAT FLUX; HEAT TRANSFER; M CODES; MELTDOWN; TEST FACILITIES; TRANSIENTS
- Descriptors DEC
- ACCIDENTS; COMPUTER CODES; ENERGY TRANSFER; REACTOR ACCIDENTS; REACTOR COMPONENTS; SIMULATION
Optional Information
- Notes
- 23 refs.