A Formal Approach for Quantitative Treatment of Modeling Uncertainties in Safety Analysis
Author:
Affiliation:
1. Korea Atomic Energy Research Institute, Integrated Safety Assessment P.O. Box 105, Yusong, Taejon, Korea, 305-600
Publisher
Informa UK Limited
Subject
Condensed Matter Physics,Nuclear Energy and Engineering,Nuclear and High Energy Physics
Link
https://www.tandfonline.com/doi/pdf/10.13182/NT96-A35296
Reference25 articles.
1. “PRA Procedures Guide,” NUREG/CR-2300, U.S. Nuclear Regulatory Commission (Jan. 1983).
2. “Severe Accident Risks: An Assessment of Five U.S. Nuclear Power Plants,” NUREG-1150, U.S. Nuclear Regulatory Commission (Dec. 1990).
3. The Concept of Probability in Safety Assessments of Technological Systems
4. A discussion on the use of judgment in representing uncertainty in PRAs
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