HTGR plant availability and reliability evaluations. Volume I. Summary of evaluations

Technical Report · Wed Dec 01 00:00:00 EST 1976

DOI:https://doi.org/10.2172/7125548· OSTI ID:7125548

Cadwallader, G. J.; Hannaman, G. W.; Jacobsen, F. K.; Stokely, R. J.

The report (1) describes a reliability assessment methodology for systematically locating and correcting areas which may contribute to unavailability of new and uniquely designed components and systems, (2) illustrates the methodology by applying it to such components in a high-temperature gas-cooled reactor (Public Service Company of Colorado's Fort St. Vrain 330-MW(e) HTGR), and (3) compares the results of the assessment with actual experience. The methodology can be applied to any component or system; however, it is particularly valuable for assessments of components or systems which provide essential functions, or the failure or mishandling of which could result in relatively large economic losses.

• Research Organization: General Atomics, San Diego, CA (United States)
• DOE Contract Number: EY-76-C-03-0167-050
• OSTI ID: 7125548
• Report Number(s): GA-A-14011(Vol.1); TRN: 77-006171
• Country of Publication: United States
• Language: English

Related Subjects

21 SPECIFIC NUCLEAR REACTORS AND ASSOCIATED PLANTS
HTGR TYPE REACTORS
AVAILABILITY
REACTOR COMPONENTS
RELIABILITY
FAILURE MODE ANALYSIS
VRAIN REACTOR
ENRICHED URANIUM REACTORS
GAS COOLED REACTORS
GRAPHITE MODERATED REACTORS
HELIUM COOLED REACTORS
POWER REACTORS
REACTORS
SYSTEM FAILURE ANALYSIS
SYSTEMS ANALYSIS
210300* - Power Reactors
Nonbreeding
Graphite Moderated