MELCOR 1.8.2 calculations of selected sequences for the ABWR

Technical Report · Fri Jul 01 04:00:00 EDT 1994

DOI:https://doi.org/10.2172/10177514· OSTI ID:10177514

Kmetyk, L N

This report summarizes the results from MELCOR calculations of severe accident sequences in the ABWR and presents comparisons with MAAP calculations for the same sequences. MELCOR was run for two low-pressure and three high-pressure sequences to identify the materials which enter containment and are available for release to the environment (source terms), to study the potential effects of core-concrete interaction, and to obtain event timings during each sequence; the source terms include fission products and other materials such as those generated by core-concrete interactions. Sensitivity studies were done on the impact of assuming limestone rather than basaltic concrete and on the effect of quenching core debris in the cavity compared to having hot, unquenched debris present.

• Research Organization: Sandia National Labs., Albuquerque, NM (United States)
• Sponsoring Organization: Nuclear Regulatory Commission, Washington, DC (United States)
• DOE Contract Number: AC04-94AL85000
• OSTI ID: 10177514
• Report Number(s): SAND--94-0938; ON: DE94017783; BR: GB0103012
• Country of Publication: United States
• Language: English

Related Subjects

21 SPECIFIC NUCLEAR REACTORS AND ASSOCIATED PLANTS
210100
22 GENERAL STUDIES OF NUCLEAR REACTORS
220502
220900
BWR TYPE REACTORS
COMPUTER CALCULATIONS
CONCRETES
CONTAINMENT
CORIUM
FISSION PRODUCT RELEASE
HEAT TRANSFER
HYDRAULICS
INTERACTIONS
M CODES
POWER REACTORS
NONBREEDING
LIGHT-WATER MODERATED
BOILING WATER COOLED
RADIOACTIVE EFFLUENTS
REACTOR ACCIDENTS
REACTOR SAFETY
SOURCE TERMS