Core-melt source reduction system to terminate an LWR core-melt accident
Conference
·
· Transactions of the American Nuclear Society; (United States)
OSTI ID:6681638
- Oak Ridge National Lab., TN (United States)
One of the design, safety, and licensing issues for the next generation of light water reactors (LWRs) is, [open quotes]What approach should be used to terminate a reactor core-melt accident and ensure no reactor containment failure in the unlikely event of an accident that results in core debris melting through the reactor vessel onto the concrete containment floor [close quotes] The safety concerns are that the molten core material will (a) melt through the concrete (thus penetrating the containment) and (b) generate noncondensable/burnable gases (thus pressurizing the containment and threatening its integrity). Noncondensable gases include burnable hydrogen (H[sub 2]) and carbon mnoxide (CO) generated primarily from the reaction of zirconium with concrete decomposition products (water and carbon dioxide). A new approach to eliminate these concerns is described herein and is called the core-melt source reduction system (COMSORS) which involves placing glass under the reactor vessel.
- OSTI ID:
- 6681638
- Report Number(s):
- CONF-921102--
- Conference Information:
- Journal Name: Transactions of the American Nuclear Society; (United States) Journal Volume: 66
- Country of Publication:
- United States
- Language:
- English
Similar Records
Core-Melt Source Reduction System (COMSORS) to terminate LWR core-melt accidents
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Termination of light-water reactor core-melt accidents with a chemical core catcher: the core-melt source reduction system (COMSORS)
Conference
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Mon Dec 07 23:00:00 EST 1992
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OSTI ID:6639068
Core-Melt Source Reduction System (COMSORS) to terminate LWR core-melt accidents
Conference
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Mon Dec 07 23:00:00 EST 1992
·
OSTI ID:10122072
Termination of light-water reactor core-melt accidents with a chemical core catcher: the core-melt source reduction system (COMSORS)
Technical Report
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Sun Sep 01 00:00:00 EDT 1996
·
OSTI ID:453914
Related Subjects
21 SPECIFIC NUCLEAR REACTORS AND ASSOCIATED PLANTS
210100 -- Power Reactors
Nonbreeding
Light-Water Moderated
Boiling Water Cooled
210200 -- Power Reactors
Nonbreeding
Light-Water Moderated
Nonboiling Water Cooled
22 GENERAL STUDIES OF NUCLEAR REACTORS
220900* -- Nuclear Reactor Technology-- Reactor Safety
ACCIDENTS
AFTER-HEAT REMOVAL
CONTAINMENT
COOLING
GLASS
MELTDOWN
MELTING
PHASE TRANSFORMATIONS
REACTOR ACCIDENTS
REACTOR SAFETY
REACTORS
REMOVAL
SAFETY
THERMAL ANALYSIS
WATER COOLED REACTORS
210100 -- Power Reactors
Nonbreeding
Light-Water Moderated
Boiling Water Cooled
210200 -- Power Reactors
Nonbreeding
Light-Water Moderated
Nonboiling Water Cooled
22 GENERAL STUDIES OF NUCLEAR REACTORS
220900* -- Nuclear Reactor Technology-- Reactor Safety
ACCIDENTS
AFTER-HEAT REMOVAL
CONTAINMENT
COOLING
GLASS
MELTDOWN
MELTING
PHASE TRANSFORMATIONS
REACTOR ACCIDENTS
REACTOR SAFETY
REACTORS
REMOVAL
SAFETY
THERMAL ANALYSIS
WATER COOLED REACTORS