Ranking significant phenomena in physical systems
The analysis of any physical system requires a thorough understanding of the principal phenomena affecting the behavior of that system. In a complex application such as a nuclear reactor, identifying the principal phenomena in an accident transient can be a formidable task. This paper describes the use of the analytical hierarchy process to assimilate engineering judgements that relate and rank the thermal-hydraulic phenomena affecting the response of a nuclear reactor. The analytical hierarchy process is described to acquaint the reader with the methodology. The importance criterion against which phenomena are selected, measured, and ranked is discussed and defined for the example application described here. The purpose of the analysis, in this case to determine the applicability of a computer code to represent the system phenomena, is defined. The hierarchy used to structure the pairwise decisions is developed in terms of both the importance criterion and the goal of assessing computer code applicability. The methodology is applied to a loss-of-feedwater transient in a nuclear reactor as an example. The analysis shows the application of engineering judgement based on experimental and calculational experience to rank both the system components and the local phenomena within those components relative to each other on a pairwise basis. The same engineering experience is used to assess the validity of the final results. The application of the overall ranking to a code applicability and uncertainty assessment is then discussed. 4 refs., 7 figs., 5 tabs.
- Research Organization:
- EG and G Idaho, Inc., Idaho Falls, ID (USA)
- Sponsoring Organization:
- DOE/NE
- DOE Contract Number:
- AC07-76ID01570
- OSTI ID:
- 6980366
- Report Number(s):
- EGG-M-89106; CONF-891103--71; ON: DE90010983
- Country of Publication:
- United States
- Language:
- English
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Related Subjects
220200 -- Nuclear Reactor Technology-- Components & Accessories
220900* -- Nuclear Reactor Technology-- Reactor Safety
99 GENERAL AND MISCELLANEOUS
990200 -- Mathematics & Computers
ACCIDENTS
COMPUTER CODES
COOLING SYSTEMS
DECISION MAKING
ENERGY SYSTEMS
ENERGY TRANSFER
FAILURE MODE ANALYSIS
FLUID MECHANICS
HEAT TRANSFER
HYDRAULICS
LOSS OF COOLANT
MATRICES
MECHANICS
NUCLEAR FACILITIES
NUCLEAR POWER PLANTS
POWER PLANTS
REACTOR ACCIDENTS
REACTOR COMPONENTS
REACTOR COOLING SYSTEMS
REACTOR SAFETY
SAFETY
SYSTEM FAILURE ANALYSIS
SYSTEMS ANALYSIS
THERMAL POWER PLANTS
TRANSIENTS