Published 1989 | Version v1
Report Open

Large break loss-of-coolant accident analyses for the high flux isotope reactor

  • 1. Oak Ridge National Lab., TN (USA)

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.

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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).

Optional Information

Contract/Grant/Project number
Contract AC05-84OR21400