Core cooling success criteria analyses to support PRA study of GE SBWR plant design
- 1. ENEL-Direzione Studi e Recerche, Rome (Italy)
- 2. ENEL-Direzione Studi e Ricerche, Pisa (Italy). Centro Ricerche Termiche e Nucleari
Description
In the framework of the cooperation program between ENEL and General Electric in the design of SBWR Light Water Passive Plant, core cooling success criteria for short term have been evaluated by ENEL by performing a thermal-hydraulic LOCA analysis with the TRACG computer code. A number of different break sizes, in the range of large, medium, and small LOCA, and location have been evaluated to define the minimum systems configuration in accordance with the acceptance criteria to limit the PCT (Peak Cladding Temperature) below 2,200 F. Particular attention was given to the efficiency of the main safety and non safety systems (CRD, GDCS, IC, and ADS), with a major interest to the passive ones (GDCS,IC). This paper does not consider the activity of the PCCS (Passive Containment Cooling System) because of its influence on the containment behavior and not specifically on the vessel core cooling. Timing sensitivity analyses for operator actions to operate a specific system or to perform recovery actions have been also evaluated
Additional details
Publishing Information
- Publisher
- American Society of Mechanical Engineers.
- Imprint Place
- New York, NY (United States)
- ISBN
- 0-7918-0636-7
- Imprint Title
- 2nd ASME-JSME international conference on nuclear engineering -- 1993
- Imprint Pagination
- 770 p.
- Journal Page Range
- p. 287-299.
Conference
- Title
- 2. Japan Society of Mechanical Engineers (JSME)/American Society of Mechanical Engineers (ASME) joint international conference on nuclear engineering.
- Dates
- 21-24 Mar 1993.
- Place
- San Francisco, CA (United States).
INIS
- Country of Publication
- United States
- Country of Input or Organization
- United States
- INIS RN
- 25058691
- Subject category
- S21: SPECIFIC NUCLEAR REACTORS AND ASSOCIATED PLANTS;
- Resource subtype / Literary indicator
- Conference, Numerical Data
- Descriptors DEI
- BWR TYPE REACTORS; ECCS; GRAVITATION; LOSS OF COOLANT; MITIGATION; NATURAL CONVECTION; PERFORMANCE; REACTOR OPERATORS; RISK ASSESSMENT; SCRAM; SENSITIVITY ANALYSIS; T CODES; THEORETICAL DATA
- Descriptors DEC
- ACCIDENTS; COMPUTER CODES; CONVECTION; DATA; ENERGY TRANSFER; ENGINEERED SAFETY SYSTEMS; ENRICHED URANIUM REACTORS; HEAT TRANSFER; INFORMATION; NUMERICAL DATA; PERSONNEL; POWER REACTORS; REACTOR ACCIDENTS; REACTOR PROTECTION SYSTEMS; REACTOR SHUTDOWN; REACTORS; SHUTDOWN; THERMAL REACTORS; WATER COOLED REACTORS; WATER MODERATED REACTORS
Optional Information
- Secondary number(s)
- CONF-930352--.