Large break loss-of-coolant accident analyses for the high flux isotope reactor
Description
The US Department of Energy's High Flux Isotope Reactor (HFIR) was analyzed to evaluate it's response to a spectrum of loss-of-coolant accidents (LOCAs) with potential for leading to core damage. The MELCOR severe accident analysis code (version 1.7.1) was used to evaluate the overall dynamic response of HFIR. Before conducting LOCA analyses, the steady-state thermal-hydraulic parameters evaluated by MELCOR for various loop sections were verified against steady-state operating data. Thereafter, HFIR depressurization tests were simulated to evaluate the system pressure change for a given depletion in coolant inventory. Interesting and important safety-related phenomena were observed. The current analyses (which should be considered preliminary) that occur over a period from 1 to 3 seconds do not lead to core wide fuel melting. Core fluid flashing during the initial rapid depressurization does cause fuel temperature excursions due to adiabatic-like heatup. 3 refs., 4 figs
Availability note (English)
MF available from INIS under the Report Number; Available from NTIS, PC A02/MF A01 as DE90001361; OSTI; INIS; US Govt. Printing Office Dep.Files
21023730.pdf
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Additional details
Publishing Information
- Imprint Pagination
- 10 p.
- Report number
- CONF-891027--3
Conference
- Title
- International symposium on research reactor safety, operations and modifications.
- Dates
- 23-27 Oct 1989.
- Place
- Chalk River, ON (Canada).
INIS
- Country of Publication
- United States
- Country of Input or Organization
- United States
- INIS RN
- 21023730
- Subject category
- S61: RADIATION PROTECTION AND DOSIMETRY; S21: SPECIFIC NUCLEAR REACTORS AND ASSOCIATED PLANTS; S22: GENERAL STUDIES OF NUCLEAR REACTORS;
- Resource subtype / Literary indicator
- Conference
- Descriptors DEI
- BENCHMARKS; COMPUTERIZED SIMULATION; DEPRESSURIZATION; HEAT TRANSFER; HFIR REACTOR; HYDRAULICS; L CODES; LOSS OF COOLANT; M CODES; PIPES; REACTOR ACCIDENTS; REACTOR COOLING SYSTEMS; REACTOR SAFETY; REACTOR VESSELS; STEADY-STATE CONDITIONS; TRANSIENTS; VALVES; VERIFICATION
- Descriptors DEC
- ACCIDENTS; COMPUTER CODES; CONTAINERS; CONTROL EQUIPMENT; COOLING SYSTEMS; ENERGY TRANSFER; ENRICHED URANIUM REACTORS; EQUIPMENT; FLOW REGULATORS; IRRADIATION REACTORS; ISOTOPE PRODUCTION REACTORS; REACTOR COMPONENTS; REACTORS; RESEARCH AND TEST REACTORS; RESEARCH REACTORS; SAFETY; SIMULATION; TANK TYPE REACTORS; TEST FACILITIES; TEST REACTORS; THERMAL REACTORS; WATER COOLED REACTORS; WATER MODERATED REACTORS
Optional Information
- Contract/Grant/Project number
- Contract AC05-84OR21400