Depressurization to mitigate direct containment heating
Creators
Description
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
Additional details
Publishing Information
- Journal Title
- Transactions of the American Nuclear Society
- Journal Volume
- 57
- Series
- Trans. Am. Nucl. Soc.
- Journal Page Range
- 160-161
- ISSN
- 0003-018X
- CODEN
- TANSA
Conference
- Title
- Joint meeting of the European Nuclear Society and the American Nuclear Society.
- Dates
- 30 Oct - 4 Nov 1988.
- Place
- Washington, DC (USA).
INIS
- Country of Publication
- United States
- Country of Input or Organization
- United States
- INIS RN
- 21014193
- Subject category
- S61: RADIATION PROTECTION AND DOSIMETRY; S21: SPECIFIC NUCLEAR REACTORS AND ASSOCIATED PLANTS;
- Resource subtype / Literary indicator
- Conference
- Descriptors DEI
- CONTAINMENT SYSTEMS; DEPRESSURIZATION; HEAT TRANSFER; HYDRAULICS; LOSS OF COOLANT; MELTDOWN; MITIGATION; PRESSURE VESSELS; PWR TYPE REACTORS; R CODES; REACTOR ACCIDENTS; REACTOR COOLING SYSTEMS; REACTOR CORE DISRUPTION; REACTOR SAFETY; S CODES; SENSITIVITY ANALYSIS
- Descriptors DEC
- ACCIDENTS; COMPUTER CODES; CONTAINERS; CONTAINMENT; COOLING SYSTEMS; ENERGY TRANSFER; ENRICHED URANIUM REACTORS; POWER REACTORS; REACTOR COMPONENTS; REACTORS; SAFETY; THERMAL REACTORS; WATER COOLED REACTORS; WATER MODERATED REACTORS
Optional Information
- Secondary number(s)
- CONF-881011--.