Comparison of the behavior of Westinghouse and combustion engineering NPPS during a small break loss of coolant accident
Description
Comparison is made between RELAP5 computations of the worst case Small Break Loss of Coolant Accident (SBLOCA) for a Westinghouse (W) RESAR-3S plant and a Combustion Engineering (CE) System 80 plant. The results indicate substantial differences in expected behaviors due to geometrical differences between the two plants and differences in the high pressure safety injection system (HPSI) characteristics. Predictions indicate that core uncovery in the CE System 80 plant would occur much later than it would occur in the Westinghouse RESAR-3S plant. In addition, the study indicates substantial sensitivity to both modeling techniques and computer code models. Thus, computations of this transient must be carefully examined before conclusions are drawn by the analyst and/or regulators
Additional details
Publishing Information
- Publisher
- American Nuclear Society.
- Imprint Place
- La Grange Park, IL (USA)
- Imprint Title
- Proceedings of international nuclear power plant thermal hydraulics and operations topical meeting
- Journal Page Range
- p. L12-1-L12-10.
Conference
- Title
- International thermal hydraulics and plant operations topical meeting.
- Dates
- 22-24 Oct 1984.
- Place
- Taipei, Taiwan (China).
INIS
- Country of Publication
- United States
- Country of Input or Organization
- United States
- INIS RN
- 18083179
- Subject category
- S21: SPECIFIC NUCLEAR REACTORS AND ASSOCIATED PLANTS;
- Resource subtype / Literary indicator
- Conference
- Descriptors DEI
- CE STANDARD REACTOR; COMPARATIVE EVALUATIONS; COMPUTERIZED SIMULATION; DRYOUT; HEAT TRANSFER; HIGH PRESSURE COOLANT INJECTIO; HYDRAULICS; LOSS OF COOLANT; PERFORMANCE; REACTOR PROTECTION SYSTEMS; SENSITIVITY; SYSTEM FAILURE ANALYSIS; WESTINGHOUSE STANDARD REACTOR
- Descriptors DEC
- ACCIDENTS; ECCS; ENERGY TRANSFER; ENRICHED URANIUM REACTORS; EVALUATION; POWER REACTORS; PWR TYPE REACTORS; REACTOR ACCIDENTS; REACTORS; SIMULATION; SYSTEMS ANALYSIS; THERMAL REACTORS; WATER COOLED REACTORS; WATER MODERATED REACTORS