Ex-vessel releases of radionuclides during molten core/concrete interactions in severe light water reactor accidents
Journal Article
·
· Nuclear Science and Engineering; (United States)
OSTI ID:5299855
- 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), Journal Name: Nuclear Science and Engineering; (United States) Vol. 111:1; ISSN 0029-5639; ISSN NSENA
- Country of Publication:
- United States
- Language:
- English
Similar Records
Uncertainty in the ex-vessel source term caused by uncertainty in in-vessel models
Independent analysis of selected core-concrete interaction and fission product release experiments with CORCON-MOD2 and VANESA
Gas bubbling-enhanced film boiling of Freon-11 on liquid metal pools. [PWR; BWR]
Conference
·
Mon Dec 31 23:00:00 EST 1984
·
OSTI ID:5982700
Independent analysis of selected core-concrete interaction and fission product release experiments with CORCON-MOD2 and VANESA
Conference
·
Tue Dec 31 23:00:00 EST 1985
·
OSTI ID:5839434
Gas bubbling-enhanced film boiling of Freon-11 on liquid metal pools. [PWR; BWR]
Conference
·
Mon Dec 31 23:00:00 EST 1984
·
OSTI ID:5869187
Related Subjects
21 SPECIFIC NUCLEAR REACTORS AND ASSOCIATED PLANTS
210100 -- Power Reactors
Nonbreeding
Light-Water Moderated
Boiling Water Cooled
22 GENERAL STUDIES OF NUCLEAR REACTORS
220900* -- Nuclear Reactor Technology-- Reactor Safety
99 GENERAL AND MISCELLANEOUS
990200 -- Mathematics & Computers
ACCIDENTS
AEROSOLS
ALKALINE EARTH METALS
ATWS
BOUNDARY CONDITIONS
BUILDING MATERIALS
BWR TYPE REACTORS
C CODES
COLLOIDS
COMPUTER CODES
CONCRETES
CONTAINERS
D CODES
DISPERSIONS
ELEMENTS
ENRICHED URANIUM REACTORS
ENVIRONMENTAL TRANSPORT
M CODES
MASS TRANSFER
MATERIALS
MELTDOWN
METALS
NATIONAL ORGANIZATIONS
NIOBIUM
POWER REACTORS
RADIONUCLIDE MIGRATION
REACTOR ACCIDENTS
REACTOR COMPONENTS
REACTOR CORES
REACTOR VESSELS
REACTORS
SOLS
STRONTIUM
THERMAL REACTORS
TRANSITION ELEMENTS
US NRC
US ORGANIZATIONS
V CODES
WATER COOLED REACTORS
WATER MODERATED REACTORS
210100 -- Power Reactors
Nonbreeding
Light-Water Moderated
Boiling Water Cooled
22 GENERAL STUDIES OF NUCLEAR REACTORS
220900* -- Nuclear Reactor Technology-- Reactor Safety
99 GENERAL AND MISCELLANEOUS
990200 -- Mathematics & Computers
ACCIDENTS
AEROSOLS
ALKALINE EARTH METALS
ATWS
BOUNDARY CONDITIONS
BUILDING MATERIALS
BWR TYPE REACTORS
C CODES
COLLOIDS
COMPUTER CODES
CONCRETES
CONTAINERS
D CODES
DISPERSIONS
ELEMENTS
ENRICHED URANIUM REACTORS
ENVIRONMENTAL TRANSPORT
M CODES
MASS TRANSFER
MATERIALS
MELTDOWN
METALS
NATIONAL ORGANIZATIONS
NIOBIUM
POWER REACTORS
RADIONUCLIDE MIGRATION
REACTOR ACCIDENTS
REACTOR COMPONENTS
REACTOR CORES
REACTOR VESSELS
REACTORS
SOLS
STRONTIUM
THERMAL REACTORS
TRANSITION ELEMENTS
US NRC
US ORGANIZATIONS
V CODES
WATER COOLED REACTORS
WATER MODERATED REACTORS