Depressurization to mitigate direct containment heating
R. Chambers, D.J. Hanson, R.J. Dallman, Fuat Odar
Abstract
R. Chambers, D.J. Hanson, R.J. Dallman, Fuat Odar
Abstract
Direct containment heating (DCH) can potentially occur during certain pressurized water reactor (PWR) severe accidents after core melt and high-pressure melt ejection from the reactor pressure vessel (RPV). Molten core material is dispersed into the containment and a rapid transfer of energy to the containment atmosphere follows. The resultant rise in the temperature and pressure could cause the containment to fail relatively early in the accident sequence. Depressurization of the reactor coolant system (RCS) is a proposed accident management strategy to reduce the DCH contribution to early containment failure. An analysis evaluating the effectiveness of this strategy has been conducted. The capability to depressurize a three-loop PWR during a TMLB' sequence (loss of alternating current power and feedwater) using the pressurizer power-operated relief valves (PORVs) and the RPV head vent was analyzed using the SCDAP/RELAP5 computer code.
A significance statement is not available in the OpenAlex record.
A contribution statement is not available in the OpenAlex record.
Method details are not available in the OpenAlex metadata.
Findings are not separately available in the OpenAlex metadata.
Limitations are not available in the OpenAlex metadata.
Application details are not available in the OpenAlex metadata.
Direct containment heating (DCH) can potentially occur during certain pressurized water reactor (PWR) severe accidents after core melt and high-pressure melt ejection from the reactor pressure vessel (RPV). Molten core material is dispersed into the containment and a rapid transfer of energy to the containment atmosphere follows. The resultant rise in the temperature and pressure could cause the containment to fail relatively early in the accident sequence. Depressurization of the reactor coolant system (RCS) is a proposed accident management strategy to reduce the DCH contribution to early containment failure. An analysis evaluating the effectiveness of this strategy has been conducted. The capability to depressurize a three-loop PWR during a TMLB' sequence (loss of alternating current power and feedwater) using the pressurizer power-operated relief valves (PORVs) and the RPV head vent was analyzed using the SCDAP/RELAP5 computer code.
Key concepts: Cabin pressurization, Containment (computer programming), Nuclear engineering, Pressurizer, Reactor pressure vessel, Pressurized water reactor, Boiler feedwater, Coolant