Modular high-temperature gas-cooled reactor core heatup accident simulations

Conference · Sun Jan 01 00:00:00 EST 1989

OSTI ID:6519430

Ball, S J; Conklin, J C

The design features of the modular high-temperature gas-cooled reactor (HTGR) have the potential to make it essentially invulnerable to damage from postulated core heatup accidents. Simulations of long-term loss-of-forced-convection (LOFC) accidents, both with and without depressurization of the primary coolant and with only passive cooling available to remove afterheat, have shown that maximum core temperatures stay below the point at which fuel failures and fission product releases are expected. Sensitivity studies also have been done to determine the effects of errors in the predictions due both to uncertainties in the modeling and to the assumptions about operational parameters. 4 refs., 5 figs.

• Research Organization: Oak Ridge National Lab., TN (USA)
• DOE Contract Number: AC05-84OR21400
• OSTI ID: 6519430
• Report Number(s): CONF-890360-2; ON: DE89007205
• Resource Relation: Conference: Eastern multiconference, Tampa, FL, USA, 28 Mar 1989; Other Information: Portions of this document are illegible in microfiche products
• Country of Publication: United States
• Language: English

Related Subjects

22 GENERAL STUDIES OF NUCLEAR REACTORS
21 SPECIFIC NUCLEAR REACTORS AND ASSOCIATED PLANTS
HTGR TYPE REACTORS
REACTOR COOLING SYSTEMS
COMPUTERIZED SIMULATION
HEAT TRANSFER
HEATING
HYDRAULICS
LOSS OF COOLANT
M CODES
REACTOR CORES
REACTOR SAFETY
ACCIDENTS
COMPUTER CODES
COOLING SYSTEMS
ENERGY SYSTEMS
ENERGY TRANSFER
FLUID MECHANICS
GAS COOLED REACTORS
GRAPHITE MODERATED REACTORS
MECHANICS
REACTOR ACCIDENTS
REACTOR COMPONENTS
REACTORS
SAFETY
SIMULATION
220900* - Nuclear Reactor Technology- Reactor Safety
210300 - Power Reactors
Nonbreeding
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