An approach for assessing ALWR passive safety system reliability [electronic resource].
- Published:
- Rockville, Md. : U.S. Nuclear Regulatory Commission, 1991.
Oak Ridge, Tenn. : Distributed by the Office of Scientific and Technical Information, U.S. Dept. of Energy. - Physical Description:
- Pages: (17 pages) : digital, PDF file
- Additional Creators:
- Sandia National Laboratories, U.S. Nuclear Regulatory Commission, and United States. Department of Energy. Office of Scientific and Technical Information
Access Online
- Restrictions on Access:
- Free-to-read Unrestricted online access
- Summary:
- Many advanced light water reactor designs incorporate passive rather than active safety features for front-line accident response. A method for evaluating the reliability of these passive systems in the context of probabilistic risk assessment has been developed at Sandia National Laboratories. This method addresses both the component (e.g. valve) failure aspect of passive system failure, and uncertainties in system success criteria arising from uncertainties in the system's underlying physical processes. These processes provide the system's driving force; examples are natural circulation and gravity-induced injection. This paper describes the method, and provides some preliminary results of application of the approach to the Westinghouse AP600 design.
- Report Numbers:
- E 1.99:sand-91-1459c
E 1.99: conf-911079--15
conf-911079--15
sand-91-1459c - Subject(s):
- Other Subject(s):
- Bwr Type Reactors
- Reactor Safety
- Pwr Type Reactors
- Circulating Systems
- Design
- Engineered Safety Systems
- Failures
- Heat Transfer
- Hydraulics
- Loss Of Coolant
- Reactor Components
- Reliability
- Risk Assessment
- Accidents
- Energy Transfer
- Enriched Uranium Reactors
- Fluid Mechanics
- Mechanics
- Power Reactors
- Reactor Accidents
- Reactors
- Safety
- Thermal Reactors
- Water Cooled Reactors
- Water Moderated Reactors
- Note:
- Published through SciTech Connect.
01/01/1991.
"sand-91-1459c"
" conf-911079--15"
"DE92004013"
19. Nuclear Regulatory Commission (NRC) water reactor safety information meeting, Bethesda, MD (United States), 28-30 Oct 1991.
Hake, T M. - Funding Information:
- AC04-76DP00789
View MARC record | catkey: 14368501