Severe core degradation analysis for an advanced reactor concept using SCDAP/RELAP5

Conference · Sun Nov 30 23:00:00 EST 1997

OSTI ID:552128

Hering, W; Homann, Ch; Sengpiel, W ^[1]

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1. Forschungszentrum Karlsruhe (Germany); and others

At the Forschungszentrum Karlsruhe (FZK), Institute of Reactor Safety (IRS), severe core degradation analyses were performed for advanced pressurized water reactor (PWR) concepts using the CSARP version of the code system SCDAP/RELAP5 mod.3.1 Rel. D. Within our work for advanced PWR concepts the whole primary circuit, the most important parts of the secondary circuit, and the reactor safety system are modeled. As an example, a small break loss of coolant accident is discussed up to formation of a pool of molten core material. Moreover, the influence of model improvements, code options, and code deficiencies are discussed. 8 refs., 3 figs., 1 tab.

• Research Organization: American Nuclear Society, La Grange Park, IL (United States)
• OSTI ID: 552128
• Report Number(s): CONF-970607--Vol.2
• Country of Publication: United States
• Language: English

Related Subjects

21 SPECIFIC NUCLEAR REACTORS AND ASSOCIATED PLANTS
22 GENERAL STUDIES OF NUCLEAR REACTORS
ENGINEERED SAFETY SYSTEMS
LOSS OF COOLANT
MELTDOWN
PRIMARY COOLANT CIRCUITS
PWR TYPE REACTORS
R CODES
S CODES
SECONDARY COOLANT CIRCUITS