Reliability analysis of the residual heat removal systems for a 300 MW(e) GCFR

Technical Report · Sun Jan 01 04:00:00 EST 1978

DOI:https://doi.org/10.2172/5011174· OSTI ID:5011174

Kelly, Jr., A. P.; Taniguchi, T.

The report represents a summary or work accomplished as part of a Department of Energy (DOE) funded program of safety studies for the gas-cooled fast breeder reactor (GCFR). The work involved an analysis of the reliability of the residual heat removal (RHR) systems for a 300 MW(e) GCFR demonstration plant design. Qualitative and quantitative reliability techniques were employed to critique the conceptual designs of the RHR systems and support systems under various operation assumptions, to indicate areas in which the reliability might be improved or for which closer analysis might be desirable. It is concluded that, in principle, the two independent RHR systems employed in the GCFR design are capable of meeting a design objective of failure of less than 10/sup -6/ per reactor year but that support systems envisioned for the current design would probably not adequately support such an objective. Other areas relating to the adequacy of RHR system diversity are also identified where closer analysis is warranted.

• Research Organization: General Atomic Co., San Diego, Calif. (USA)
• DOE Contract Number: EY-76-C-03-0167-023
• OSTI ID: 5011174
• Report Number(s): GA-A-14653
• Country of Publication: United States
• Language: English

Related Subjects

21 SPECIFIC NUCLEAR REACTORS AND ASSOCIATED PLANTS
210500* -- Power Reactors
Breeding
BREEDER REACTORS
CALCULATION METHODS
COOLING SYSTEMS
DESIGN
EPITHERMAL REACTORS
FAILURES
FAST REACTORS
FBR TYPE REACTORS
GAS COOLED REACTORS
GCFR REACTOR
GCFR TYPE REACTORS
HELIUM COOLED REACTORS
PLANNING
PROBABILITY
REACTOR COMPONENTS
REACTOR COOLING SYSTEMS
REACTORS
RELIABILITY
RHR SYSTEMS