Integrated Reliability and Risk Analysis System (IRRAS) Version 2. 0 user's guide

Technical Report · Fri Jun 01 00:00:00 EDT 1990

DOI:https://doi.org/10.2172/6888085· OSTI ID:6888085

Russell, K D; Sattison, M B ^[1]; Rasmuson, D M ^[2]

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1. EG and G Idaho, Inc., Idaho Falls, ID (USA)
2. Nuclear Regulatory Commission, Washington, DC (USA). Div. of Systems Research

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. Also provided in the system is an integrated full-screen editor for use when interfacing with remote mainframe computer systems. 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 2.0 and is the subject of this user's guide. Version 2.0 of IRRAS provides all of the same capabilities as Version 1.0 and adds a relational data base facility for managing the data, improved functionality, and improved algorithm performance. 9 refs., 292 figs., 4 tabs.

• Research Organization: Nuclear Regulatory Commission, Washington, DC (USA). Div. of Systems Research; EG and G Idaho, Inc., Idaho Falls, ID (USA)
• Sponsoring Organization: NRC
• DOE Contract Number: AC07-76ID01570
• OSTI ID: 6888085
• Report Number(s): NUREG/CR-5111; EGG--2535; ON: TI90012904
• Country of Publication: United States
• Language: English

Related Subjects

22 GENERAL STUDIES OF NUCLEAR REACTORS
220900* -- Nuclear Reactor Technology-- Reactor Safety
99 GENERAL AND MISCELLANEOUS
990200 -- Mathematics & Computers
ALGORITHMS
COMPUTER CODES
COMPUTER PROGRAM DOCUMENTATION
DATA COVARIANCES
FAILURE MODE ANALYSIS
FAILURES
FAULT TREE ANALYSIS
I CODES
MATHEMATICAL LOGIC
NUCLEAR FACILITIES
NUCLEAR POWER PLANTS
POWER PLANTS
PROBABILISTIC ESTIMATION
REACTOR SAFETY
RELIABILITY
RISK ASSESSMENT
SAFETY
SYSTEM FAILURE ANALYSIS
SYSTEMS ANALYSIS
THERMAL POWER PLANTS