An Improved Probabilistic Fracture Mechanics Model for Pressurized Thermal Shock
This paper provides an overview of an improved probabilistic fracture mechanics (PFM) model used for calculating the conditional probabilities of fracture and failure of a reactor pressure vessel (RPV) subjected to pressurized-thermal-shock (PTS) transients. The updated PFM model incorporates several new features: expanded databases for the fracture toughness properties of RPV steels; statistical representations of the fracture toughness databases developed through application of rigorous mathematical procedures; and capability of generating probability distributions for RPV fracture and failure. The updated PFM model was implemented into the FAVOR fracture mechanics program, developed at Oak Ridge National Laboratory as an applications tool for RPV integrity assessment; an example application of that implementation is discussed herein. Applications of the new PFM model are providing essential input to a probabilistic risk assessment (PRA) process that will establish an improved technical basis for re-assessment of current PTS regulations by the US Nuclear Regulatory Commission (NRC). The methodology described herein should be considered preliminary and subject to revision in the PTS re-evaluation process.
- Research Organization:
- Oak Ridge National Lab. (ORNL), Oak Ridge, TN (United States)
- Sponsoring Organization:
- Nuclear Regulatory Commission (US)
- DOE Contract Number:
- AC05-00OR22725
- OSTI ID:
- 788581
- Report Number(s):
- P01-111365; TRN: US200203%%157
- Resource Relation:
- Conference: Structural Mechanics in Reactor Technology, Washington, DC (US), 08/13/2001--08/17/2001; Other Information: PBD: 29 Oct 2001
- Country of Publication:
- United States
- Language:
- English
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