MELCOR 1.8.5 Sensitivity Study of Molten Core Concrete Interaction Experiment, SWICCS-1, 2 and 3
Creators
- 1. Korea Institute of Nuclear Safety, Taejon (Korea, Republic of)
Description
In a postulated core melt accident, if the molten core is not retained in-vessel despite taking severe accident mitigation actions, the core debris will relocate in the reactor cavity region. There, it will interact with structural concrete and could potentially result in basemat failure (through erosion or overpressurization) and consequent fission product release to the environment. Although a methodology of cooling the molten core by adding water on its top is selected as a severe accident management strategy in case molten core is released outside a reactor vessel, the possibility of a long-term cooling is still unresolved. In the OECD/MCCI project scheduled for 4 years from 2002. 1 to 2005. 12, a series of tests are being performed to secure the data for cooling the molten core spread out at the reactor cavity and for the long-term CCI (Core Concrete Interaction). In this study, SWICCS-1, 2 and 3, of the SWICCS tests of OECD/MCCI project, was assessed using MELCOR1.8.5 and the sensitivity parameters' selection of CAV package were investigated in SWICCS-1 and the same options were applied to another experiments SWICCS-2 and -3
Additional details
Publishing Information
- Publisher
- KNS
- Imprint Place
- Taejon (Korea, Republic of)
- Imprint Title
- Proceedings of the KNS autumn meeting
- Imprint Pagination
- [1 CD-ROM]
- Journal Page Range
- [2 p.]
Conference
- Title
- 2006 autumn meeting of the KNS
- Dates
- 2-3 Nov 2006
- Place
- Kyongju (Korea, Republic of)
INIS
- Country of Publication
- Korea, Republic of
- Country of Input or Organization
- Korea, Republic of
- INIS RN
- 38049485
- Subject category
- S22: GENERAL STUDIES OF NUCLEAR REACTORS;
- Resource subtype / Literary indicator
- Conference, Non-conventional Literature
- Descriptors DEI
- CONCRETES; FISSION PRODUCT RELEASE; FISSION PRODUCTS; M CODES; REACTOR ACCIDENTS; REACTOR VESSELS; SENSITIVITY ANALYSIS
- Descriptors DEC
- ACCIDENTS; BUILDING MATERIALS; COMPUTER CODES; CONTAINERS; ISOTOPES; MATERIALS; RADIOACTIVE MATERIALS
Optional Information
- Notes
- 5 refs, 5 figs, 2 tabs