Probabilistic Pressure Boundary Integrity Safety Assessment (PISA) Program
June 13, 2013 — The U. S. Nuclear Regulatory Commission (NRC) requires leading-edge technical support to ensure the safety & reliability of pressurized components in U.S. nuclear power plants (NPP).
FAVOR (Fracture Analysis of Vessels - Oak Ridge)
June 13, 2013 — On behalf of the NRC, ORNL is helping to: Finalize and/or develop technical bases for revision of 10 CFR 50.61(a); Appendix G to 10 CFR Part 50; and RG 1.154, “Format and Content of Plant-Specific Pressurized Thermal Shock Safety Analysis Reports for Pressurized-Water Reactors,” based on an amalgamation of recent research advancements. Extend existing technical understanding and analysis methodologies so that they can be used to perform probabilistic safety assessments of the mechanical integrity of pressurized components in general, and not be limited in their validated applicability to only the beltline region of the reactor pressure vessel (RPV).
June 13, 2013 — On behalf of the NRC, ORNL is helping to organize and develop the project entitled: Development of Predictive Models of Neutron Irradiation Embrittlement in Reactor Pressure Vessel Steels to Support Worldwide Efforts on Nuclear Power Plant Life Extension.