Event Sequence Quantification for a Loss of Shutdown Cooling Accident in the GCFR
Conference
·
OSTI ID:5811946
- General Atomics, San Diego, CA (United States)
A summary is presented of the core-wide sequence of events of a postulated total loss of forced and natural convection decay heat removal in a shutdown Gas-Cooled Fast Reactor (GCFR). It outlines the analytical methods and results for the progression of the accident sequence. This hypothetical accident proceeds in the distinct phases of cladding melting, assembly wall melting and molten steel relocation into the interassembly spacing, and fuel relocation. It identifies the key phenomena of the event sequence and the concerns and mechanisms of both recriticality and recriticality prevention.
- Research Organization:
- General Atomics, San Diego, CA (United States)
- Sponsoring Organization:
- USDOE National Nuclear Security Administration (NNSA), Nuclear Criticality Safety Program (NCSP)
- DOE Contract Number:
- AT03-76SF71023
- OSTI ID:
- 5811946
- Report Number(s):
- GA-A-15556; CONF-790816-84
- Country of Publication:
- United States
- Language:
- English
Similar Records
Comparative Safety Assessment of Upflow Versus Downflow GCFR Core Designs
Assessment of a Core Meltdown in the Gas-Cooled Fast Breeder Reactor with an Upflow Core
Core meltdown assessment in the GCFR
Technical Report
·
Mon Sep 01 00:00:00 EDT 1980
·
OSTI ID:6771881
Assessment of a Core Meltdown in the Gas-Cooled Fast Breeder Reactor with an Upflow Core
Technical Report
·
Sun Jul 01 00:00:00 EDT 1979
·
OSTI ID:5744906
Core meltdown assessment in the GCFR
Technical Report
·
Tue May 01 00:00:00 EDT 1979
·
OSTI ID:6071690
Related Subjects
11 NUCLEAR FUEL CYCLE AND FUEL MATERIALS
21 SPECIFIC NUCLEAR REACTORS AND ASSOCIATED PLANTS
210500 -- Power Reactors
Breeding
220900* -- Nuclear Reactor Technology-- Reactor Safety
ACCIDENTS
AFTER-HEAT REMOVAL
Assembly Wall Melting
BREEDER REACTORS
COOLING SYSTEMS
CRITICALITY
Cladding Melting
Core Auxiliary Cooling System (CACS)
EPITHERMAL REACTORS
FAILURES
FAST REACTORS
FBR TYPE REACTORS
FLUID FLOW
Fission Power
Fuel Relocation
GAS COOLED REACTORS
GCFR REACTOR
GCFR TYPE REACTORS
Gas-Cooled Fast Reactor (GCFR)
HELIUM COOLED REACTORS
Interassembly Spacing
LIQUID FLOW
Loss of Shutdown Cooling (LOSC) Accident
MELTDOWN
Molten Steel Relocation
Nuclear Criticality Safety Program (NCSP)
REACTOR ACCIDENTS
REACTOR COMPONENTS
REACTOR COOLING SYSTEMS
REACTOR SAFETY
REACTOR SHUTDOWN
REACTORS
REMOVAL
RHR SYSTEMS
SAFETY
SHUTDOWNS
Slumped CORe Integrated Analysis (SCORIA)
21 SPECIFIC NUCLEAR REACTORS AND ASSOCIATED PLANTS
210500 -- Power Reactors
Breeding
220900* -- Nuclear Reactor Technology-- Reactor Safety
ACCIDENTS
AFTER-HEAT REMOVAL
Assembly Wall Melting
BREEDER REACTORS
COOLING SYSTEMS
CRITICALITY
Cladding Melting
Core Auxiliary Cooling System (CACS)
EPITHERMAL REACTORS
FAILURES
FAST REACTORS
FBR TYPE REACTORS
FLUID FLOW
Fission Power
Fuel Relocation
GAS COOLED REACTORS
GCFR REACTOR
GCFR TYPE REACTORS
Gas-Cooled Fast Reactor (GCFR)
HELIUM COOLED REACTORS
Interassembly Spacing
LIQUID FLOW
Loss of Shutdown Cooling (LOSC) Accident
MELTDOWN
Molten Steel Relocation
Nuclear Criticality Safety Program (NCSP)
REACTOR ACCIDENTS
REACTOR COMPONENTS
REACTOR COOLING SYSTEMS
REACTOR SAFETY
REACTOR SHUTDOWN
REACTORS
REMOVAL
RHR SYSTEMS
SAFETY
SHUTDOWNS
Slumped CORe Integrated Analysis (SCORIA)