The LOCA performance of the AP600 passive safety systems
Creators
- 1. Westinghouse Electric Corp., Pittsburgh, PA (United States)
- 2. National Nuclear Corp. Ltd., Cheshire (United Kingdom)
Description
The AP600 is an advanced passive safeguards pressurized water reactor (PWR) that is being developed jointly by Westinghouse Electric Corporation, the U.S. Department of Energy, and the Electrical Power Research Institute. The plant has a thermal rating of 1940 MW (thermal) [600 MW(electric)] and has been designed with passive safeguard systems that utilize gravity feed injection rather than safety-grade active pumps and equipment. Calculations performed for a range of break sizes used locations to find the worst set of conditions for depressurizing the reactor coolant system. The main criterion was system inventory such that the core remained covered. The resulting break spectrum study indicates only that the double-ended guillotine shear of the direct vessel injection line (a .68-in. line that feeds the emergency core coolant flow into the vessel) resulted in a momentary core uncover. For all other small-break cases, the core remained covered as the reactor coolant system depressurized. The passive safety systems provided sufficient mass flow to the reactor vessel such that even under the more conservative Appendix K assumptions, the core remained covered and in a coolable state. The LOCA analysis performed for the AP600 confirms that passive safety systems can provide the core cooling necessary to meet the requirements of 10CFR50.46 with ample margin
Additional details
Publishing Information
- Journal Title
- Transactions of the American Nuclear Society
- Journal Volume
- 66
- Journal Page Range
- p. 601-603.
- ISSN
- 0003-018X
- CODEN
- TANSAO
Conference
- Title
- past, present, and future.
- Acronym
- Joint American Nuclear Society (ANS)/European Nuclear Society (ENS) international meeting on fifty years of controlled nuclear chain reaction
- Dates
- 15-20 Nov 1992.
- Place
- Chicago, IL (United States).
INIS
- Country of Publication
- United States
- Country of Input or Organization
- United States
- INIS RN
- 24050823
- Subject category
- S21: SPECIFIC NUCLEAR REACTORS AND ASSOCIATED PLANTS;
- Resource subtype / Literary indicator
- Conference
- Descriptors DEI
- AFTER-HEAT REMOVAL; CORE FLOODING SYSTEMS; DEPRESSURIZATION; HYDRAULICS; LOSS OF COOLANT; N CODES; PWR TYPE REACTORS; REACTOR SAFETY; T CODES; THERMAL ANALYSIS; W CODES
- Descriptors DEC
- ACCIDENTS; COMPUTER CODES; ECCS; ENGINEERED SAFETY SYSTEMS; ENRICHED URANIUM REACTORS; POWER REACTORS; REACTOR ACCIDENTS; REACTOR PROTECTION SYSTEMS; REACTORS; REMOVAL; SAFETY; THERMAL REACTORS; WATER COOLED REACTORS; WATER MODERATED REACTORS
Optional Information
- Secondary number(s)
- CONF-921102--.