Post-accident core coolability of light water reactors

Journal Article · Fri Apr 01 04:00:00 EST 1983 · Energy Dev. Jpn.; (United States)

OSTI ID:5348252

Michio, I; Teruo, I; Tomio, Y; Tsutao, H

A study on post-accident core coolability of LWR is discussed based on the practical fuel failure behavior experienced in NSRR, PBF, PNS and others. The fuel failure behavior at LOCA, RIA and PCM conditions are reviewed, and seven types of fuel failure modes are extracted as the basic failure mechanism at accident conditions. These are: cladding melt or brittle failure, molten UO/sub 2/ failure, high temperature cladding burst, low temperature cladding burst, failure due to swelling of molten UO/sub 2/, failure due to cracks of embrittled cladding for irradiated fuel rods, and TMI-2 core failure. The post-accident core coolability at each failure mode is discussed. The fuel failures caused actual flow blockage problems. A characteristic which is common among these types is that the fuel rods are in the conditions violating the present safety criteria for accidents, and UO/sub 2/ pellets are in melting or near melting hot conditions when the fuel rods failed.

• Research Organization: Division of Reactor Safety, Japan Energy Research Institute
• OSTI ID: 5348252
• Journal Information: Energy Dev. Jpn.; (United States), Journal Name: Energy Dev. Jpn.; (United States) Vol. 5:3; ISSN EDJAD
• Country of Publication: United States
• Language: English

Related Subjects

22 GENERAL STUDIES OF NUCLEAR REACTORS
220300 -- Nuclear Reactor Technology-- Fuel Elements
220900* -- Nuclear Reactor Technology-- Reactor Safety
ACCIDENTS
ACTINIDE COMPOUNDS
AFTER-HEAT REMOVAL
CHALCOGENIDES
COOLING
EMBRITTLEMENT
FAILURE MODE ANALYSIS
FLOW BLOCKAGE
FUEL ELEMENT FAILURE
FUEL ELEMENTS
FUEL PELLETS
FUEL RODS
FUEL-CLADDING INTERACTIONS
LOSS OF COOLANT
MELTING
OXIDES
OXYGEN COMPOUNDS
PELLETS
PHASE TRANSFORMATIONS
REACTIVITY
REACTIVITY INSERTIONS
REACTOR ACCIDENTS
REACTOR COMPONENTS
REACTOR CORE DISRUPTION
REACTOR SAFETY
REACTORS
REMOVAL
SAFETY
SWELLING
SYSTEM FAILURE ANALYSIS
SYSTEMS ANALYSIS
URANIUM COMPOUNDS
URANIUM DIOXIDE
URANIUM OXIDES
WATER COOLED REACTORS