SARA: An expert system for assisting in safety reviews
Conference
·
· Transactions of the American Nuclear Society; (United States)
OSTI ID:7168538
Expert systems make it possible to capture and computerize complex decision-making processes. This provides a new and effective method for managing and applying engineering procedures. For several years, Sargent and Lundy has been pursuing the application of this technology and applying it to the engineering review process. One example of efforts is the Safety Review Advisor (SARA), an engineering support program being developed for the Electric Power Research Institute (EPRI). SARA helps engineers perform safety reviews, particularly those required by 10CFR50.59.
- OSTI ID:
- 7168538
- Report Number(s):
- CONF-911107--
- Conference Information:
- Journal Name: Transactions of the American Nuclear Society; (United States) Journal Volume: 63
- Country of Publication:
- United States
- Language:
- English
Similar Records
SARA; An expert system for assisting in safety reviews
Expert systems for assisting in design reviews
Safety review advisor
Conference
·
Mon Dec 31 23:00:00 EST 1990
· Proceedings of the American Power Conference; (United States)
·
OSTI ID:6174484
Expert systems for assisting in design reviews
Conference
·
Sun Dec 31 23:00:00 EST 1989
· Proceedings of the American Power Conference; (United States)
·
OSTI ID:5907240
Safety review advisor
Conference
·
Sat Dec 31 23:00:00 EST 1988
·
OSTI ID:6471832
Related Subjects
21 SPECIFIC NUCLEAR REACTORS AND ASSOCIATED PLANTS
210100 -- Power Reactors
Nonbreeding
Light-Water Moderated
Boiling Water Cooled
210200 -- Power Reactors
Nonbreeding
Light-Water Moderated
Nonboiling Water Cooled
22 GENERAL STUDIES OF NUCLEAR REACTORS
220900* -- Nuclear Reactor Technology-- Reactor Safety
99 GENERAL AND MISCELLANEOUS
990200 -- Mathematics & Computers
AUTOMATION
BWR TYPE REACTORS
COMMERCIALIZATION
DATA BASE MANAGEMENT
DECISION MAKING
DESIGN
DISASTERS
DOCUMENT TYPES
DOCUMENTATION
ENGINEERED SAFETY SYSTEMS
ENRICHED URANIUM REACTORS
EPRI
EXPERT SYSTEMS
FAILURES
FIRES
FLOODS
INFORMATION SYSTEMS
KNOWLEDGE BASE
LICENSING
MANAGEMENT
NATIONAL ORGANIZATIONS
POWER REACTORS
PWR TYPE REACTORS
QUALITY ASSURANCE
REACTOR LICENSING
REACTOR SAFETY
REACTORS
REGULATIONS
REVIEWS
SAFETY
TESTING
THERMAL REACTORS
US NRC
US ORGANIZATIONS
WATER COOLED REACTORS
WATER MODERATED REACTORS
210100 -- Power Reactors
Nonbreeding
Light-Water Moderated
Boiling Water Cooled
210200 -- Power Reactors
Nonbreeding
Light-Water Moderated
Nonboiling Water Cooled
22 GENERAL STUDIES OF NUCLEAR REACTORS
220900* -- Nuclear Reactor Technology-- Reactor Safety
99 GENERAL AND MISCELLANEOUS
990200 -- Mathematics & Computers
AUTOMATION
BWR TYPE REACTORS
COMMERCIALIZATION
DATA BASE MANAGEMENT
DECISION MAKING
DESIGN
DISASTERS
DOCUMENT TYPES
DOCUMENTATION
ENGINEERED SAFETY SYSTEMS
ENRICHED URANIUM REACTORS
EPRI
EXPERT SYSTEMS
FAILURES
FIRES
FLOODS
INFORMATION SYSTEMS
KNOWLEDGE BASE
LICENSING
MANAGEMENT
NATIONAL ORGANIZATIONS
POWER REACTORS
PWR TYPE REACTORS
QUALITY ASSURANCE
REACTOR LICENSING
REACTOR SAFETY
REACTORS
REGULATIONS
REVIEWS
SAFETY
TESTING
THERMAL REACTORS
US NRC
US ORGANIZATIONS
WATER COOLED REACTORS
WATER MODERATED REACTORS