Published 1997 | Version v1
Journal article Metadata-only

Analysis of the molten core/concrete interaction using the MELCOR 1.8.3 code for a typical Korean nuclear power plant

Creators

  • 1. Seoul National Univ. (Korea, Republic of)
  • 2. Korea Power Engineering Co., Inc., Kyunggi-do (Korea, Republic of)

Description

MELCOR calculations for molten core/concrete interaction (MCCI) under severe accident conditions are performed to understand the physical phenomena of MCCI with a comparison of four selected experiments. Also, with the aid of MELCOR 1.8.3, the responses of the reactor cavity on MCCI are evaluated for a safety assessment of a typical Korean nuclear power plant under severe accident conditions

Additional details

Publishing Information

Journal Title
Transactions of the American Nuclear Society
Journal Volume
77
Journal Page Range
p. 288-290.
ISSN
0003-018X
CODEN
TANSAO

Conference

Title
1997 American Nuclear Society (ANS) winter meeting.
Dates
16-20 Nov 1997.
Place
Albuquerque, NM (United States).

INIS

Country of Publication
United States
Country of Input or Organization
United States
INIS RN
29021053
Subject category
S99: GENERAL AND MISCELLANEOUS;
Resource subtype / Literary indicator
Conference
Descriptors DEI
CONCRETES; EMISSION; FLUID-STRUCTURE INTERACTIONS; M CODES; MELTDOWN; RADIOACTIVE AEROSOLS; REACTOR SAFETY
Descriptors DEC
ACCIDENTS; AEROSOLS; BUILDING MATERIALS; COLLOIDS; COMPUTER CODES; DISPERSIONS; MATERIALS; REACTOR ACCIDENTS; SAFETY; SOLS

Optional Information

Secondary number(s)
CONF-971125--.