Integrated Reliability and Risk Analysis System (IRRAS): Version 2.5 (Reference Manual)

Technical Report · Thu Feb 28 23:00:00 EST 1991

DOI:https://doi.org/10.2172/5888929· OSTI ID:5888929

Russell, K. D. ^[1]; McKay, M. K. ^[1]; Sattison, M. B. ^[1]; Skinner, N. L. ^[1]; Wood, S. T. ^[1]; Rasmuson, D M ^[2]

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1. EG and G Idaho, Inc., Idaho Falls, ID (United States)
2. US Nuclear Regulatory Commission (NRC), Washington, DC (United States)

The Integrated Reliability and Risk Analysis System (IRRAS) is a state-of-the-art, microcomputer-based probabilistic risk assessment (PRA) model development and analysis tool to address key nuclear plant safety issues. IRRAS is an integrated software tool that gives the user the ability to create and analyze fault trees and accident sequences using a microcomputer. This program provides functions that range from graphical fault tree construction to cut set generation and quantification. Version 1.0 of the IRRAS program was released in February of 1987. Since that time, many user comments and enhancements have been incorporated into the program providing a much more powerful and user-friendly system. This version has been designated IRRAS 2.5 and is the subject of this Reference Manual. Version 2.5 of IRRAS provides the same capabilities as Version 1.0 and adds a relational data base facility for managing the data, improved functionality, and improved algorithm performance.

• Research Organization: US Nuclear Regulatory Commission (NRC), Washington, DC (United States). Office of Nuclear Regulatory Research; EG and G Idaho, Inc., Idaho Falls, ID (United States)
• Sponsoring Organization: USNRC; USDOE
• DOE Contract Number: AC07-76ID01570
• OSTI ID: 5888929
• Report Number(s): NUREG/CR--5300-Vol.1; EGG--2613-Vol.1; ON: TI91010575
• Country of Publication: United States
• Language: English

Related Subjects

22 GENERAL STUDIES OF NUCLEAR REACTORS
220100 -- Nuclear Reactor Technology-- Theory & Calculation
220900* -- Nuclear Reactor Technology-- Reactor Safety
ACCIDENTS
ALGORITHMS
COMPUTER CODES
COMPUTER GRAPHICS
COMPUTER OUTPUT DEVICES
COMPUTERIZED SIMULATION
COMPUTERS
DATA BASE MANAGEMENT
DOCUMENT TYPES
ELECTRONIC CIRCUITS
FAULT TREE ANALYSIS
I CODES
MANAGEMENT
MANUALS
MATHEMATICAL LOGIC
MICROELECTRONIC CIRCUITS
MICROPROCESSORS
MODIFICATIONS
NUCLEAR FACILITIES
NUCLEAR POWER PLANTS
PERFORMANCE
POWER PLANTS
PROBABILISTIC ESTIMATION
REACTOR ACCIDENTS
REACTOR SAFETY
RISK ASSESSMENT
SAFETY
SIMULATION
SYSTEM FAILURE ANALYSIS
SYSTEMS ANALYSIS
THERMAL POWER PLANTS