Published 1996 | Version v1
Report Open

A direct comparison of MELCOR 1.8.3 and MAAP4 results for several PWR ampersand BWR accident sequences

Creators

  • 1. ITS Corp. Albuquerque NM (United States)
  • 2. Sandia National Labs., Albuquerque, NM (United States)
  • 3. NUPEC, Minato-ku, Tokyo (Japan)

Description

This paper presents a comparison of calculations of severe accident progression for several postulated accident sequences for representative Pressurized Water Reactors (PWR) and Boiling Water Reactors (BWR) nuclear power plants performed with the MELCOR 1.8.3 and the MAAP4 computer codes. The PWR system examined in this study is a 1100 MWe system similar in design to a Westinghouse 3-loop plant with a large dry containment; the BWR is a 1100 MWe system similar in design to General Electric BWR/4 with a Mark I containment. A total of nine accident sequences were studied with both codes. Results of these calculations are compared to identify major differences in the timing of key events in the calculated accident progression or other important aspects of severe accident behavior, and to identify specific sources of the observed differences

Availability note (English)

MF available from INIS under the Report Number; Also available from OSTI as DE96014078; NTIS; US Govt. Printing Office Dep.

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Additional details

Publishing Information

Imprint Pagination
9 p.
Report number
SAND--96-2053C

Conference

Title
International topical meeting on probabilistic safety assessment - moving toward risk based regulation.
Dates
29 Sep - 3 Oct 1996.
Place
Park City, UT (United States).

INIS

Country of Publication
United States
Country of Input or Organization
United States
INIS RN
28001871
Subject category
S21: SPECIFIC NUCLEAR REACTORS AND ASSOCIATED PLANTS; S21: SPECIFIC NUCLEAR REACTORS AND ASSOCIATED PLANTS; S99: GENERAL AND MISCELLANEOUS;
Resource subtype / Literary indicator
Conference
Descriptors DEI
BWR TYPE REACTORS; COMPARATIVE EVALUATIONS; CORIUM; FAILURE MODE ANALYSIS; HEAT TRANSFER; HYDRAULICS; M CODES; PWR TYPE REACTORS; REACTOR ACCIDENTS; REACTOR SAFETY
Descriptors DEC
ACCIDENTS; COMPUTER CODES; ENERGY TRANSFER; ENRICHED URANIUM REACTORS; EVALUATION; POWER REACTORS; REACTORS; SAFETY; SYSTEM FAILURE ANALYSIS; SYSTEMS ANALYSIS; THERMAL REACTORS; WATER COOLED REACTORS; WATER MODERATED REACTORS

Optional Information

Contract/Grant/Project number
Contract AC04-94AL85000
Funding organization
USDOE, Washington, DC (United States).
Secondary number(s)
CONF-960912--29.