Materials Reliability Program: Phase II Work Plan for Developing a Risk-Informed Approach for Calculating Reactor Pressure Vessel Heatup and Cooldown Operating Curves (MRP-195)
The current procedures for calculating pressure-temperature (P/T) limits for normal reactor heatup and cooldown are defined by the deterministic fracture mechanics methodology in Appendix G (in both Section XI and Section III) of the ASME Code. The recent pressurized thermal shock (PTS) reevaluation effort used a very thorough probabilistic fracture mechanics (PFM) evaluation to develop a technical basis to increase the PTS screening criteria. This same PFM methodology can be applied for evaluating normal heatup and cooldown operation for both PWRs and BWRs. Recently completed proof-of-concept studies (EPRI reports 1009546, 1011691, and 1011742) indicated that probabilistic concepts can be used to develop a risk-informed, deterministic calculation method for generating P/T limit curves for normal reactor heatup and cooldown.
- Research Organization:
- Electric Power Research Insitute
- Sponsoring Organization:
- USDOE - Office of Nuclear Energy, Science and Technology (NE)
- DOE Contract Number:
- FC07-03ID14536
- OSTI ID:
- 883009
- Report Number(s):
- 1013619
- Country of Publication:
- United States
- Language:
- English
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