Published 2006 | Version v1
Miscellaneous

MELCOR 1.8.5 Sensitivity Study of Molten Core Concrete Interaction Experiment, SWICCS-1, 2 and 3

  • 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

Part of:
Proceedings of the KNS autumn meeting

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