Hypothetical accident scenario analyses for a 250-MW(t) modular high temperature gas-cooled reactor

Conference · Fri Nov 01 04:00:00 EST 1985

OSTI ID:5048680

Harrington, R M; Ball, S J; Cleveland, J C

This paper describes calculations performed to characterize the inherent safety of a 250-MW(t), 100-MW(e), pebble bed modular high temperature gas-cooled reactor (HTGR) design with vertical in-line arrangement (i.e., upflow core with steam generators directly above the core). A variety of postulated accident sequences involving combinations of loss of forced primary coolant (helium) circulation, loss of primary coolant pressurization, and loss of heat sink were studied and were discussed.

• Research Organization: Oak Ridge National Lab., TN (USA)
• DOE Contract Number: AC05-84OR21400
• OSTI ID: 5048680
• Report Number(s): CONF-851125-15; ON: TI86002179
• Country of Publication: United States
• Language: English

Related Subjects

21 SPECIFIC NUCLEAR REACTORS AND ASSOCIATED PLANTS
210300 -- Power Reactors
Nonbreeding
Graphite Moderated
22 GENERAL STUDIES OF NUCLEAR REACTORS
220900* -- Nuclear Reactor Technology-- Reactor Safety
ACCIDENTS
GAS COOLED REACTORS
GRAPHITE MODERATED REACTORS
HEAT SINKS
HOMOGENEOUS REACTORS
HTGR TYPE REACTORS
LOSS OF FLOW
LOSSES
PEBBLE BED REACTORS
REACTOR ACCIDENTS
REACTOR SAFETY
REACTORS
SAFETY
SINKS
SOLID HOMOGENEOUS REACTORS