A perspective of PC-based probabilistic risk assessment
Conference
·
OSTI ID:5291589
Probabilistic risk assessment (PRA) information has been under-utilized in the past due to the large effort required to input the PRA data and the large expense of the computers needed to run PRA codes. The microcomputer-based Integrated Reliability and Risk Analysis System (IRRAS) and the System Analysis and Risk Assessment (SARA) System, under development at the Idaho National Engineering Laboratory, have greatly enhanced the ability of managers to use PRA techniques in their decision-making. IRRAS is a tool that allows an analyst to create, modify, update, and reanalyze a plant PRA to keep the risk assessment current with the plant's configuration and operation. The SARA system is used to perform sensitivity studies on the results of a PRA. This type of analysis can be used to evaluate proposed changes to a plant or its operation. The success of these two software projects demonstrate that risk information can be made readily available to those that need it. This is the first step in the development of a true risk management capability.
- Research Organization:
- EG and G Idaho, Inc., Idaho Falls (USA); Nuclear Regulatory Commission, Washington, DC (USA). Office of Nuclear Regulatory Research
- DOE Contract Number:
- AC07-76ID01570
- OSTI ID:
- 5291589
- Report Number(s):
- EGG-M-33687; CONF-871234-14; ON: DE88006715
- Country of Publication:
- United States
- Language:
- English
Similar Records
Microcomputer-based probabilistic risk assessment for nuclear power plant safety studies
System Analysis and Risk Assessment (SARA) system
System Analysis and Risk Assessment (SARA) system
Conference
·
Wed Dec 31 23:00:00 EST 1986
·
OSTI ID:5226258
System Analysis and Risk Assessment (SARA) system
Conference
·
Sat Oct 25 00:00:00 EDT 1986
·
OSTI ID:7037689
System Analysis and Risk Assessment (SARA) system
Conference
·
Tue Dec 31 23:00:00 EST 1985
·
OSTI ID:5832591
Related Subjects
22 GENERAL STUDIES OF NUCLEAR REACTORS
220900* -- Nuclear Reactor Technology-- Reactor Safety
99 GENERAL AND MISCELLANEOUS
990220 -- Computers
Computerized Models
& Computer Programs-- (1987-1989)
AVAILABILITY
COMPUTER CODES
COMPUTERS
DATA BASE MANAGEMENT
DECISION MAKING
DIGITAL COMPUTERS
FAULT TREE ANALYSIS
I CODES
MAINTENANCE
MANAGEMENT
NUCLEAR FACILITIES
NUCLEAR POWER PLANTS
PERSONAL COMPUTERS
POWER PLANTS
PROBABILITY
REACTOR SAFETY
RELIABILITY
RISK ASSESSMENT
S CODES
SAFETY
SENSITIVITY ANALYSIS
SYSTEM FAILURE ANALYSIS
SYSTEMS ANALYSIS
THERMAL POWER PLANTS
220900* -- Nuclear Reactor Technology-- Reactor Safety
99 GENERAL AND MISCELLANEOUS
990220 -- Computers
Computerized Models
& Computer Programs-- (1987-1989)
AVAILABILITY
COMPUTER CODES
COMPUTERS
DATA BASE MANAGEMENT
DECISION MAKING
DIGITAL COMPUTERS
FAULT TREE ANALYSIS
I CODES
MAINTENANCE
MANAGEMENT
NUCLEAR FACILITIES
NUCLEAR POWER PLANTS
PERSONAL COMPUTERS
POWER PLANTS
PROBABILITY
REACTOR SAFETY
RELIABILITY
RISK ASSESSMENT
S CODES
SAFETY
SENSITIVITY ANALYSIS
SYSTEM FAILURE ANALYSIS
SYSTEMS ANALYSIS
THERMAL POWER PLANTS