An approach for assessing ALWR passive safety system reliability
Conference
·
OSTI ID:10107109
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.
- Research Organization:
- Sandia National Labs., Albuquerque, NM (United States)
- Sponsoring Organization:
- Nuclear Regulatory Commission, Washington, DC (United States)
- DOE Contract Number:
- AC04-76DP00789
- OSTI ID:
- 10107109
- Report Number(s):
- SAND--91-1459C; CONF-911079--15; ON: DE92004013
- Country of Publication:
- United States
- Language:
- English
Similar Records
An approach for assessing ALWR passive safety system reliability
Assessment of ALWR passive safety system reliability. Phase 1: Methodology development and component failure quantification
Integration of the reliability of passive system in probabilistic safety assessment
Conference
·
Mon Dec 31 23:00:00 EST 1990
·
OSTI ID:6148691
Assessment of ALWR passive safety system reliability. Phase 1: Methodology development and component failure quantification
Technical Report
·
Fri Mar 31 23:00:00 EST 1995
·
OSTI ID:48627
Integration of the reliability of passive system in probabilistic safety assessment
Conference
·
Thu Jul 01 00:00:00 EDT 2004
·
OSTI ID:21160633
Related Subjects
21 SPECIFIC NUCLEAR REACTORS AND ASSOCIATED PLANTS
210100
210200
22 GENERAL STUDIES OF NUCLEAR REACTORS
220900
BWR TYPE REACTORS
CIRCULATING SYSTEMS
DESIGN
ENGINEERED SAFETY SYSTEMS
FAILURES
HEAT TRANSFER
HYDRAULICS
LOSS OF COOLANT
POWER REACTORS
NONBREEDING
LIGHT-WATER MODERATED
BOILING WATER COOLED
POWER REACTORS
NONBREEDING
LIGHT-WATER MODERATED
NONBOILING WATER COOLED
PWR TYPE REACTORS
REACTOR COMPONENTS
REACTOR SAFETY
RELIABILITY
RISK ASSESSMENT
210100
210200
22 GENERAL STUDIES OF NUCLEAR REACTORS
220900
BWR TYPE REACTORS
CIRCULATING SYSTEMS
DESIGN
ENGINEERED SAFETY SYSTEMS
FAILURES
HEAT TRANSFER
HYDRAULICS
LOSS OF COOLANT
POWER REACTORS
NONBREEDING
LIGHT-WATER MODERATED
BOILING WATER COOLED
POWER REACTORS
NONBREEDING
LIGHT-WATER MODERATED
NONBOILING WATER COOLED
PWR TYPE REACTORS
REACTOR COMPONENTS
REACTOR SAFETY
RELIABILITY
RISK ASSESSMENT