Containment building atmosphere response during severe accidents in high temperature gas-cooled reactors

Conference · Tue Jan 01 04:00:00 EST 1985

OSTI ID:6496006

Kroeger, P G; Chan, B C

Several safety evaluations for large High Temperature Gas Cooled Reactors (HTGR), using a Prestressed Concrete Reactor Vessel (PCRV) design, have concluded that Unrestricted Core Heatup Accidents (UCHA) present the most important severe accidents, resulting in the dominant source term. While the core thermohydraulic transients for such accident sequences have been presented previously, the subject of this paper is the containment building (CB) atmosphere transient, with primary emphasis on the CB atmosphere temperature and pressure, as overpressurization is the most likely failure mode.

• Research Organization: Brookhaven National Lab., Upton, NY (USA)
• DOE Contract Number: AC02-76CH00016
• OSTI ID: 6496006
• Report Number(s): BNL-NUREG-37133; CONF-851007-16; ON: TI86002930
• Country of Publication: United States
• Language: English

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