MELCOR simulation of a large-break LOCA at the high-flux isotope reactor

Conference · Fri Jan 01 00:00:00 EST 1993 · Transactions of the American Nuclear Society; (United States)

OSTI ID:5799926

Morris, R H; Fisher, S E; Greene, S R ^[1]

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1. Martin Marietta Energy Systems, Inc., Oak Ridge, TN (United States)

The Oak Ridge National Laboratory has recently completed a safety analysis report (SAR) for the high-flux isotope reactor (HFIR). Because [open quotes]severe[close quotes] (core melt) accidents were an element of the HFIR's design basis, the SAR included analyses of such scenarios. A model using the MELCOR (Ref. 2) severe accident code has been developed for analysis of selected events that lead to core damage. The purpose of this paper is to discuss the calculation of the noble gas source terms to the environment following a postulated large-break loss-of-coolant accident (LOCA) at the HFIR.

• OSTI ID: 5799926
• Report Number(s): CONF-930601-; CODEN: TANSAO
• Journal Information: Transactions of the American Nuclear Society; (United States), Vol. 68; Conference: American Nuclear Society (ANS) annual meeting, San Diego, CA (United States), 20-24 Jun 1993; ISSN 0003-018X
• Country of Publication: United States
• Language: English

Related Subjects

21 SPECIFIC NUCLEAR REACTORS AND ASSOCIATED PLANTS
22 GENERAL STUDIES OF NUCLEAR REACTORS
HFIR REACTOR
DESIGN BASIS ACCIDENTS
SAFETY ANALYSIS
REACTOR ACCIDENTS
COMPUTERIZED SIMULATION
CORE FLOODING SYSTEMS
ECCS
LOSS OF COOLANT
REACTOR CORES
REACTOR SAFETY
ACCIDENTS
ENGINEERED SAFETY SYSTEMS
ENRICHED URANIUM REACTORS
IRRADIATION REACTORS
ISOTOPE PRODUCTION REACTORS
REACTOR COMPONENTS
REACTOR PROTECTION SYSTEMS
REACTORS
RESEARCH AND TEST REACTORS
RESEARCH REACTORS
SAFETY
SIMULATION
TANK TYPE REACTORS
TEST REACTORS
THERMAL REACTORS
WATER COOLED REACTORS
WATER MODERATED REACTORS
220600* - Nuclear Reactor Technology- Research
Test & Experimental Reactors
220900 - Nuclear Reactor Technology- Reactor Safety