Evaluation of uncertainties in risk emanating from a number of severe accident issues
- 1. Sandia National Labs., Albuquerque, NM (USA)
- 2. Safety and Reliability Optimization Services, Knoxville, TN (USA)
- 3. Technadyne, Albuquerque, NM (USA)
Description
A study has been performed to estimate, for a particular pressurized water reactor, the uncertainty in risk associated with a number of key phenomenological issues. A second objective was to distinguish the individual importance of the various issues as contributors to the overall uncertainty in risk. The issues considered touched upon the areas of system behavior, containment loading, containment performance, and fission product source term behavior. It was found that the most important source of uncertainty for the plant in question (Surry) was direct containment heating (i.e., the transfer of heat from the core debris to the containment atmosphere when the debris is ejected at high pressure from the reactor vessel and dispersed throughout the atmosphere). Other significant issues included hydrogen burning, containment failure pressure, aerosol agglomeration uncertainties, the frequency of check valve failures leading to a loss-of-coolant accident (LOCA) outside containment, and the potential for having a LOCA induced by high temperatures in the reactor coolant system. (orig.)
Additional details
Publishing Information
- Journal Title
- Nucl. Eng. Des.
- Journal Volume
- 104
- Journal Issue
- 3
- Series
- Nucl. Eng. Des.
- Journal Page Range
- 249-266
- ISSN
- 0029-5493
- CODEN
- NEDEA
Conference
- Title
- 3. workshop on containment integrity.
- Dates
- 21-23 May 1986.
- Place
- Washington, DC (USA).
INIS
- Country of Publication
- Netherlands
- Country of Input or Organization
- Netherlands
- INIS RN
- 19031949
- Subject category
- S61: RADIATION PROTECTION AND DOSIMETRY; S21: SPECIFIC NUCLEAR REACTORS AND ASSOCIATED PLANTS;
- Resource subtype / Literary indicator
- Conference
- Descriptors DEI
- CONTAINMENT; DATA COVARIANCES; FAILURES; FAULT TREE ANALYSIS; HEALTH HAZARDS; LOSS OF COOLANT; PROBABILITY; PWR TYPE REACTORS; REACTOR ACCIDENTS; REACTOR CORES; REGRESSION ANALYSIS; RISK ASSESSMENT; S CODES; VALVES; WEIGHTING FUNCTIONS
- Descriptors DEC
- ACCIDENTS; COMPUTER CODES; CONTROL EQUIPMENT; ENRICHED URANIUM REACTORS; EQUIPMENT; FLOW REGULATORS; FUNCTIONS; HAZARDS; MATHEMATICS; POWER REACTORS; REACTOR COMPONENTS; REACTORS; STATISTICS; SYSTEM FAILURE ANALYSIS; SYSTEMS ANALYSIS; THERMAL REACTORS; WATER COOLED REACTORS; WATER MODERATED REACTORS
Optional Information
- Contract/Grant/Project number
- Contract DE-AC04-76DP00789