Recent SCDAP/RELAP5 code applications and improvements

Conference · Sun Mar 01 04:00:00 EST 1998

OSTI ID:305912

Harvego, E A; Ghan, L S; Knudson, D L; Siefken, L J ^[1]

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1. Lockheed Martin Idaho Technology Co., Idaho Falls, ID (United States). Idaho National Engineering and Environmental Lab.

This paper summarizes (1) a recent application of the severe accident analysis code SCDAP/RELAP5/MOD3.1, and (2) development and assessment activities associated with the release of SACDAP/RELAP5/MOD3.2. The Nuclear Regulatory Commission (NRC) has been evaluating the integrity of steam generator tubes during severe accidents. MOD3.1 has been used to support that evaluation. Studies indicate that the pressurizer surge line will fail before any steam generator tubes are damaged. Thus, core decay energy would be released as steam through the surge line and the tube wall would be spared from exposure to prolonged flow of high temperature steam. The latest code version, MOD3.2, contains several improvements to models that address both the early phase and late phase of a severe accident. The impact of these improvements to the overall code capabilities has been assessed. Results of the assessment are summarized in this paper.

• Research Organization: Nuclear Regulatory Commission, Office of Nuclear Regulatory Research, Washington, DC (United States); Brookhaven National Lab., Upton, NY (United States)
• Sponsoring Organization: Nuclear Regulatory Commission, Washington, DC (United States); USDOE, Washington, DC (United States)
• DOE Contract Number: AC07-94ID13223
• OSTI ID: 305912
• Report Number(s): NUREG/CP--0162-Vol.1; CONF-9710101--Vol.1; ON: TI98007503
• Country of Publication: United States
• Language: English

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REACTOR ACCIDENTS
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THREE MILE ISLAND-2 REACTOR