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Post-accident core damage assessment using radionuclide analysis

Conference · · Trans. Am. Nucl. Soc.; (United States)
OSTI ID:5227131
None
Research Organization:
Westinghouse Electric Company, P.O. Box 2728, Pittsburgh, PA 15230
OSTI ID:
5227131
Report Number(s):
CONF-831047-
Conference Information:
Journal Name: Trans. Am. Nucl. Soc.; (United States) Journal Volume: 45
Country of Publication:
United States
Language:
English

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Related Subjects

22 GENERAL STUDIES OF NUCLEAR REACTORS
220900* -- Nuclear Reactor Technology-- Reactor Safety
ACCIDENTS
COMPUTER CODES
DAMAGE
DATA COVARIANCES
ENRICHED URANIUM REACTORS
FISSION PRODUCTS
FUEL PELLETS
FUEL-CLADDING INTERACTIONS
ISOTOPES
MATERIALS
MELTING
MONITORING
O CODES
PELLETS
PHASE TRANSFORMATIONS
POWER REACTORS
PWR TYPE REACTORS
RADIATION EFFECTS
RADIATION MONITORING
RADIOACTIVE MATERIALS
RADIOACTIVITY
REACTOR ACCIDENTS
REACTOR CORE DISRUPTION
REACTOR SHUTDOWN
REACTORS
REGULATIONS
SAMPLING
SHUTDOWNS
THERMAL REACTORS
THREE MILE ISLAND-2 REACTOR
WATER COOLED REACTORS
WATER MODERATED REACTORS