Published February 1985
| Version v1
Report
Support state modeling for the treatment of intersystem dependence in the probabilistic safety study for Italian ENEL PWR nuclear standard power stations
Description
The support state model employed in the Progetto Unificato Nucleare (PUN) Probabilistic Safety Study was an effective means for the analysis of intersystem dependencies for modeling and quantifying accident sequences. The model identifies the various plant system interactions and defines the complete spectrum of support system conditions, in such a way as to significantly reduce intersystem dependencies in frontline event trees. The support state model allows for eminent insights into the understanding of plant system dependencies and provides an immediate perception of support system failures that are critical for the safety of the plant. It is a very effective model for an accurate quantification of accident sequence frequencies
Additional details
Publishing Information
- Imprint Title
- International topical meeting on probabilistic safety methods and applications: proceedings. Volume 2. Sessions 9-16
- Journal Page Range
- p. 101.1-101.13.
- Report number
- EPRI-NP--3912-SR-Vol.2
Conference
- Title
- International ANS/ENS topical meeting on probabilistic safety methods and applications.
- Dates
- 24 Feb - 1 Mar 1985.
- Place
- San Francisco, CA (USA).
INIS
- Country of Publication
- United States
- Country of Input or Organization
- United States
- INIS RN
- 19023687
- Subject category
- S21: SPECIFIC NUCLEAR REACTORS AND ASSOCIATED PLANTS;
- Resource subtype / Literary indicator
- Conference, Non-conventional Literature
- Descriptors DEI
- FAILURE MODE ANALYSIS; FEEDWATER; LOSS OF COOLANT; OUTAGES; PWR TYPE REACTORS; REACTOR ACCIDENTS; REACTOR COOLING SYSTEMS; REACTOR SAFETY; RELIABILITY; RISK ASSESSMENT; SAFETY ENGINEERING; SYSTEMS ANALYSIS
- Descriptors DEC
- ACCIDENTS; COOLING SYSTEMS; ENRICHED URANIUM REACTORS; HYDROGEN COMPOUNDS; OXYGEN COMPOUNDS; POLAR SOLVENTS; POWER REACTORS; REACTOR COMPONENTS; REACTORS; SAFETY; SOLVENTS; SYSTEM FAILURE ANALYSIS; THERMAL REACTORS; WATER; WATER COOLED REACTORS; WATER MODERATED REACTORS