Reliability evaluations of GCFR residual heat removal systems

Conference · Fri Oct 01 04:00:00 EDT 1976

OSTI ID:7138273

Kelley, Jr., A. P.; DeLaquil, P. III

Using the component reliability data base and accident analysis methodology similar to that employed in the Reactor Safety Study, the authors have separately evaluated the likelihood of failure of core residual heat removal (RHR) for the conceptual design of a 300 MW(e) gas-cooled fast breeder (GCFR) demonstration plant. Although employing somewhat different methods, these two evaluations have arrived at similar conclusions with regard to the total probability of RHR failure, as well as the relative contributions of particular accident sequences to this total. Both studies have considered a spectrum of initiating events leading to RHR requirements and have quantified potential common cause failures within the RHR systems by use of an empirical factor relating the fraction of component common-cause failures to the total component failure rate. By these methods, the total probability of residual heat removal failure has been estimated as less than 10/sup -5/ per year, dominated by sequences involving loss of electrical power.

• Research Organization: General Atomic Co., San Diego, Calif. (USA)
• OSTI ID: 7138273
• Report Number(s): GA-A-14119; CONF-761001-19
• Country of Publication: United States
• Language: English

Related Subjects

21 SPECIFIC NUCLEAR REACTORS AND ASSOCIATED PLANTS
210500 -- Power Reactors
Breeding
22 GENERAL STUDIES OF NUCLEAR REACTORS
220900* -- Nuclear Reactor Technology-- Reactor Safety
BREEDER REACTORS
COOLING SYSTEMS
EPITHERMAL REACTORS
FAILURES
FAST REACTORS
FBR TYPE REACTORS
GAS COOLED REACTORS
GCFR REACTOR
GCFR TYPE REACTORS
HELIUM COOLED REACTORS
PROBABILITY
REACTOR COMPONENTS
REACTOR COOLING SYSTEMS
REACTORS
RELIABILITY
RHR SYSTEMS