An overview of the EBR-II PRA (Probabilistic Risk Assessment)

Conference · Sun Dec 31 23:00:00 EST 1989

OSTI ID:6991436

Hill, D J; Chang, Y W; Deitrich, L W; Ragland, W A ^[1]; Lehto, W K; Schaeffer, R W ^[2]

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1. Argonne National Lab., IL (USA)
2. Argonne National Lab., Idaho Falls, ID (USA)

Experimental Breeder Reactor-II, EBR-II, is a 60 MW(t) liquid sodium cooled, pool type fast reactor which has operated successfully as a power reactor and irradiation facility for over 25 years. Argonne National Laboratory is currently performing a Probabilistic Risk Assessment of EBR-II. An overview of the PRA is presented with special attention to those issues which are important to EBR-II such as the passive decay heat removal capabilities and the passive shut down capability provided by the reactivity feedbacks. 7 refs., 3 figs., 1 tab.

• Research Organization: Argonne National Lab., IL (USA)
• Sponsoring Organization: DOE/NE
• DOE Contract Number: W-31109-ENG-38
• OSTI ID: 6991436
• Report Number(s): CONF-900804-17; ON: DE90011095
• Country of Publication: United States
• Language: English

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ACCIDENTS
AFTER-HEAT REMOVAL
BREEDER REACTORS
COOLING SYSTEMS
EBR-2 REACTOR
ENERGY SYSTEMS
ENERGY TRANSFER
EPITHERMAL REACTORS
EXPERIMENTAL REACTORS
FAILURE MODE ANALYSIS
FAST REACTORS
FBR TYPE REACTORS
FLUID MECHANICS
HEAT TRANSFER
HUMAN FACTORS
HYDRAULICS
LIQUID METAL COOLED REACTORS
LMFBR TYPE REACTORS
LOSS OF FLOW
MECHANICS
POWER REACTORS
REACTIVITY
REACTOR ACCIDENTS
REACTOR COMPONENTS
REACTOR COOLING SYSTEMS
REACTOR SAFETY
REACTOR SHUTDOWN
REACTORS
RELIABILITY
REMOVAL
RESEARCH AND TEST REACTORS
RISK ASSESSMENT
SAFETY
SHUTDOWNS
SODIUM COOLED REACTORS
SYSTEM FAILURE ANALYSIS
SYSTEMS ANALYSIS