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Study on severe fuel damage and in-vessel melt progression

Technical Report:

Abstract

In-vessel core melt progression describes the progression of the state of a reactor core from core uncovery up to reactor vessel melt through in uncovered accidents or through temperature stabilization in accidents recovered by core reflooding. Melt progression can be thought as two parts; early melt progression and late melt progression. Early phase of core melt progression includes the progression of core material melting and relocation, which mostly consist of metallic materials. On the other hand, the late phase of core melt progression involves ceramic material melt and relocation to the lower plenum and heat-up the reactor vessel lower head. A large number of information are available for the early melt progression through experiments such as SFD, DF, FLHT test and utilized in the severe accident analysis codes. However, understanding of the late phase melt progression phenomenology is based primary on TMI-2 core examinations and not much experimental information is available. Especilally, the great uncertainties exist in vessel failure mode, melt composition, mass, and temperature. Further research is planned to perform to reduce the uncertainties in understanding of core melt down accidents as parts of long term melt progression research program. A study on the core melt progression at KAERI  More>>
Authors:
Kim, Hee Dong; Kim, Sang Baik; Lee, Gyu Jung [1] 
  1. Korea Atomic Energy Res. Inst., Taejon (Korea, Republic of)
Publication Date:
Jun 01, 1992
Product Type:
Technical Report
Report Number:
KAERI/TR-275/92
Reference Number:
SCA: 220200; PA: AIX-25:006522; EDB-94:012528; ERA-19:006655; NTS-94:014829; SN: 94001126472
Resource Relation:
Other Information: PBD: Jun 1992
Subject:
22 GENERAL STUDIES OF NUCLEAR REACTORS; REACTOR VESSELS; FUEL ELEMENT FAILURE; MELTDOWN; CLADDING; COMPUTER CODES; CONTROL ELEMENTS; FAILURE MODE ANALYSIS; FUEL RODS; REACTOR CORES; 220200; COMPONENTS AND ACCESSORIES
OSTI ID:
10112989
Research Organizations:
Korea Atomic Energy Research Inst., Daeduk (Korea, Republic of)
Country of Origin:
Korea, Republic of
Language:
Korean
Other Identifying Numbers:
Other: ON: DE94610779; TRN: KR9300132006522
Availability:
OSTI; NTIS (US Sales Only); INIS
Submitting Site:
INIS
Size:
145 p.
Announcement Date:
Jun 30, 2005

Technical Report:

Citation Formats

Kim, Hee Dong, Kim, Sang Baik, and Lee, Gyu Jung. Study on severe fuel damage and in-vessel melt progression. Korea, Republic of: N. p., 1992. Web.
Kim, Hee Dong, Kim, Sang Baik, & Lee, Gyu Jung. Study on severe fuel damage and in-vessel melt progression. Korea, Republic of.
Kim, Hee Dong, Kim, Sang Baik, and Lee, Gyu Jung. 1992. "Study on severe fuel damage and in-vessel melt progression." Korea, Republic of.
@misc{etde_10112989,
title = {Study on severe fuel damage and in-vessel melt progression}
author = {Kim, Hee Dong, Kim, Sang Baik, and Lee, Gyu Jung}
abstractNote = {In-vessel core melt progression describes the progression of the state of a reactor core from core uncovery up to reactor vessel melt through in uncovered accidents or through temperature stabilization in accidents recovered by core reflooding. Melt progression can be thought as two parts; early melt progression and late melt progression. Early phase of core melt progression includes the progression of core material melting and relocation, which mostly consist of metallic materials. On the other hand, the late phase of core melt progression involves ceramic material melt and relocation to the lower plenum and heat-up the reactor vessel lower head. A large number of information are available for the early melt progression through experiments such as SFD, DF, FLHT test and utilized in the severe accident analysis codes. However, understanding of the late phase melt progression phenomenology is based primary on TMI-2 core examinations and not much experimental information is available. Especilally, the great uncertainties exist in vessel failure mode, melt composition, mass, and temperature. Further research is planned to perform to reduce the uncertainties in understanding of core melt down accidents as parts of long term melt progression research program. A study on the core melt progression at KAERI has been being performed through the Severe Accident Research Program with USNRC. KAERI staff had participated in the PBF SFD experiments at INEL and analyses of experiments were performed using SCDAP code. Experiments of core melt program have not been carried out at KAERI yet. It is planned that further research on core melt down accidents will be performed, which is related to design of future generations of nuclear reactors as parts of long-term project for improvement of nuclear reactor safety. (Author).}
place = {Korea, Republic of}
year = {1992}
month = {Jun}
}