Actions for Collection of methods for reliability and safety engineering [electronic resource].
Collection of methods for reliability and safety engineering [electronic resource].
- Published
- Oak Ridge, Tenn. : Distributed by the Office of Scientific and Technical Information, U.S. Dept. of Energy, 1976.
- Physical Description
- Pages: 170 : digital, PDF file
- Additional Creators
- United States. Department of Energy. Office of Scientific and Technical Information
Access Online
- Restrictions on Access
- Free-to-read Unrestricted online access
- Summary
- The document presented contains five reports each describing a method of reliability and safety engineering. Report I provides a conceptual framework for the study of component malfunctions during system evaluations. Report II provides methods for locating groups of critical component failures such that all the component failures in a given group can be caused to occur by the occurrence of a single separate event. These groups of component failures are called common cause candidates. Report III provides a method for acquiring and storing system-independent component failure logic information. The information stored is influenced by the concepts presented in Report I and also includes information useful in locating common cause candidates. Report IV puts forth methods for analyzing situations that involve systems which change character in a predetermined time sequence. These phased missions techniques are applicable to the hypothetical ''accident chains'' frequently analyzed for nuclear power plants. Report V presents a unified approach to cause-consequence analysis, a method of analysis useful during risk assessments. This approach, as developed by the Danish Atomic Energy Commission, is modified to reflect the format and symbology conventionally used for other types of analysis of nuclear reactor systems.
- Report Numbers
- E 1.99:ancr-1273
ancr-1273 - Subject(s)
- Other Subject(s)
- Failure Mode Analysis
- Reviews
- Nuclear Power Plants
- Safety Engineering
- Reactor Components
- Equations
- Failures
- Mathematical Models
- Probability
- Reactor Accidents
- Reactor Safety
- Reliability
- Accidents
- Document Types
- Engineering
- Nuclear Facilities
- Power Plants
- Safety
- System Failure Analysis
- Systems Analysis
- Thermal Power Plants
- Note
- Published through SciTech Connect.
04/01/1976.
"ancr-1273"
Wilson, J.R.; Fussell, J.B.; Rasmuson, D.M.; Burdick, G.R.; Zipperer, J.C.
Idaho National Engineering Lab., Idaho Falls (USA) - Funding Information
- E(10-1)-1375
View MARC record | catkey: 14370712