Ex-vessel releases of radionuclides during molten core/concrete interactions in severe light water reactor accidents

Journal Article · Fri May 01 00:00:00 EDT 1992 · Nuclear Science and Engineering; (United States)

OSTI ID:5299855

Lee, M; Wu, J S ^[1]

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1. National Tsing-Hua Univ., Dept. of Nuclear Engineering, Hsinchu 30043 (TW)

In this paper releases of radionuclides and the production of aerosols during the molten core/concrete interaction (MCCI) phase of degraded core accidents in light water reactors are termed ex-vessel releases. The VANESA and METOXA codes were respectively developed by the U.S. Nuclear Regulatory Commission and the Industrial Degraded Core Rulemaking (IDCOR) program to quantify ex-vessel releases. Comparison of calculations by VANESA and METOXA (under identical initial and boundary conditions) show that except for niobium and strontium species, the predicted ex-vessel radionuclide release rates are within an order of magnitude of each other. In an actual application of these two codes to the source term quantification of severe accidents, the initial and boundary conditions for the calculations could be significantly different, as demonstrated in an analysis of an anticipated transient without scram accident sequence in a boiling water reactor. For the same amount of debris, the MCCI thermal-hydraulic results provided for METOXA from a DECOMP calculation tend to drive more radioactive material from the debris pool than those provided for VANESA from a CORCON/MOD2 calculation. The MAAP code, however, predicts that less mass is involved in the MCCI.

• OSTI ID: 5299855
• Journal Information: Nuclear Science and Engineering; (United States), Vol. 111:1; ISSN 0029-5639
• Country of Publication: United States
• Language: English

Related Subjects

22 GENERAL STUDIES OF NUCLEAR REACTORS
21 SPECIFIC NUCLEAR REACTORS AND ASSOCIATED PLANTS
99 GENERAL AND MISCELLANEOUS//MATHEMATICS, COMPUTING, AND INFORMATION SCIENCE
REACTOR ACCIDENTS
RADIONUCLIDE MIGRATION
AEROSOLS
ATWS
BOUNDARY CONDITIONS
BWR TYPE REACTORS
C CODES
CONCRETES
D CODES
M CODES
MELTDOWN
NIOBIUM
REACTOR CORES
REACTOR VESSELS
STRONTIUM
US NRC
V CODES
ACCIDENTS
ALKALINE EARTH METALS
BUILDING MATERIALS
COLLOIDS
COMPUTER CODES
CONTAINERS
DISPERSIONS
ELEMENTS
ENRICHED URANIUM REACTORS
ENVIRONMENTAL TRANSPORT
MASS TRANSFER
MATERIALS
METALS
NATIONAL ORGANIZATIONS
POWER REACTORS
REACTOR COMPONENTS
REACTORS
SOLS
THERMAL REACTORS
TRANSITION ELEMENTS
US ORGANIZATIONS
WATER COOLED REACTORS
WATER MODERATED REACTORS
220900* - Nuclear Reactor Technology- Reactor Safety
210100 - Power Reactors
Nonbreeding
Light-Water Moderated
Boiling Water Cooled
990200 - Mathematics & Computers