Analysis of In-Vessel Late Phase Melt Progression Using SCDAP/RELAP5/MOD3.3

Conference · Thu Jul 01 04:00:00 EDT 2004

OSTI ID:21160563

Park, R J; Kim, S B; Kim, H D ^[1]

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1. Korea Atomic Energy Research Institute, Yuseong, P.O.Box 105, Daejeon, 305-600 (Korea, Republic of)

High-pressure in-vessel melt progressions of the KSNP (Korean Standard Nuclear Power Plant) have been analyzed using the SCDAP/RELAP5/MOD3.3 computer code. The total loss of feed water (LOFW) to the steam generators with/without intentional RCS depressurization using the safety depressurization system (SDS) and the station blackout (SBO) have been simulated from transient initiation to reactor vessel failure. The SCDAP/RELAP5/MOD3.3 results have shown that the pressure boundary of the reactor coolant system did not fail before reactor vessel failure in the high-pressure sequences of the LOFW and the SBO transients of the KSNP. In all the high-pressure transients, approximately 20-30 % of the core material was melted and relocated to the lower plenum of the reactor vessel at the time of reactor vessel failure. Intentional RCS depressurization using the SDS for the total LOFW delays reactor vessel failure for approximately 5 hours by actuation of the safety injection tanks. At the time of reactor vessel failure, approximately 50-60 % of the fuel rod cladding was oxidized for the total LOFW and the SBO transients of the KSNP. (authors)

• Research Organization: American Nuclear Society, 555 North Kensington Avenue, La Grange Park, IL 60526 (United States)
• OSTI ID: 21160563
• Country of Publication: United States
• Language: English

Related Subjects

42 ENGINEERING
COMPUTER CODES
DEPRESSURIZATION
DEPRESSURIZATION SYSTEMS
FAILURES
FUEL RODS
LOSSES
NUCLEAR POWER PLANTS
OUTAGES
REACTOR COOLING SYSTEMS
REACTOR VESSELS
SAFETY
SAFETY INJECTION
SIMULATION
STEAM GENERATORS
TANKS
TRANSIENTS