Comparison of sensitivity measures in probabilistic fracture mechanics
Creators
- 1. Gesellschaft für Anlagen- und Reaktorsicherheit (GRS) gGmbH, Cologne (Germany)
- 2. Lietuvos Energetikos Institutas (LEI), Kauno Technologijos Universitetas (KTU), Kaunas (Lithuania)
- 3. Candu Energy Inc., Mississauga, Ontario (Canada)
- 4. International Atomic Energy Agency (IAEA), Vienna (Austria)
- 5. Sigma-Phase, Inc., Vail, AZ (United States)
Description
Highlights: • Sensitivity measures in probabilistic fracture mechanics are compared. • Six parameter ranking methods with different starting points are evaluated. • The proposed sensitivity measures agree in their ranking. • The sensitivity ranking approaches differ in their scope and the required effort. Probabilistic fracture mechanics (PFM) simulates the behavior of cracked structures and propagates uncertainties from input parameters to a failure probability or its uncertain estimate. In nuclear technology, this approach supports the assessment of the rupture probability of highly reliable pipes, which is an important parameter for the safety analysis of a nuclear power plant. For the appropriate probabilistic modelling of a structure with consideration of uncertainties, but also for the analysis of PFM application cases, the question arises, which input parameter of a probabilistic model has a higher impact on the estimate of computed failure probability, and which has a minor impact. This question is associated with the sensitivity measures or importance factors of the input parameters and their ranking concerning their influence. In this paper, six different approaches for the quantification of the sensitivity of parameters PFM evaluations are investigated: the amplification ratio, the direction cosine, the degree of separation, the analysis of the most probable failure point, the separation of uncertainty method, and the simple sample-based sensitivity study. Each method is described, visualized, applied to a common test case, and compared. The application case and the comparison are part of the Coordinated Research Project (CRP), "Methodology for Assessing Pipe Failure Rates in Advanced Water-Cooled Reactors (AWCRs)" by the International Atomic Energy Agency (IAEA), which is dedicated to the development of failure rates of piping in AWCRs. The participants used different PFM computer codes to analyze the test case and individual sensitivity methods to rank the input parameters, which motivated the comprehensive survey. The predicted parameter ranking of the approaches is consistent between the methods and between different PFM codes, but the approaches differ in the scope and the required effort. A conclusion is drawn and recommendations for the six different approaches are given.
Availability note (English)
Available from http://dx.doi.org/10.1016/j.ijpvp.2021.104388Additional details
Identifiers
- DOI
- 10.1016/j.ijpvp.2021.104388;
- PII
- S0308016121000867;
Publishing Information
- Journal Title
- International Journal of Pressure Vessels and Piping
- Journal Volume
- 192
- Journal Page Range
- vp.
- ISSN
- 0308-0161
- CODEN
- PRVPAS
INIS
- Country of Publication
- United Kingdom
- Country of Input or Organization
- International Atomic Energy Agency (IAEA)
- INIS RN
- 53120504
- Subject category
- S22: GENERAL STUDIES OF NUCLEAR REACTORS; S46: INSTRUMENTATION RELATED TO NUCLEAR SCIENCE AND TECHNOLOGY;
- Descriptors DEI
- COMPUTER CODES; COMPUTERIZED SIMULATION; COORDINATED RESEARCH PROGRAMS; FRACTURE MECHANICS; IAEA; NUCLEAR ENERGY; NUCLEAR POWER PLANTS; PROBABILISTIC ESTIMATION; RECOMMENDATIONS; SAFETY ANALYSIS; SENSITIVITY ANALYSIS; WATER COOLED REACTORS
- Descriptors DEC
- CALCULATION METHODS; ENERGY; INTERNATIONAL ORGANIZATIONS; MECHANICS; NUCLEAR FACILITIES; POWER PLANTS; REACTORS; RESEARCH PROGRAMS; SIMULATION; THERMAL POWER PLANTS
Optional Information
- Copyright
- Copyright (c) 2021 The Authors. Published by Elsevier Ltd.