Materials Reliability Program: Fracture Toughness Testing of Decommissioned PWR Core Internals Material Samples (MRP-160) Non-Proprietary Version
Technical Report
·
OSTI ID:860571
Pressurised water reactor (PWR) cores operate under extreme envrionmental conditions due to coolant chemistry, operating temperature and neutron exposure. Extending the life of PWRs requires detailed knowledge of teh changes in mechanical and corrosion properties of teh structural austenitic stainless steel components adjacent to the fuel. This report contains results of fracture toughness testing of samples machined from decommissioned PWR reactor internals.
- Research Organization:
- Electric Power Research Institute
- Sponsoring Organization:
- USDOE - Office of Nuclear Energy, Science and Technology (NE)
- DOE Contract Number:
- FC07-03ID14536
- OSTI ID:
- 860571
- Report Number(s):
- 1012655; Task 8
- Country of Publication:
- United States
- Language:
- English
Similar Records
Characterization of Decommissioned PWR Vessel Internals Materials Samples: Material Certification, Fluence, and Temperature (Nonproprietary Version)
Characterization of Decommissioned PWR Vessel Internals Material Samples: Tensile and SSRT Testing (Nonproprietary Version)
Materials Reliability Program: Environmental Fatigue Testing of Type 304L Stainless Steel U-Bends in Simulated PWR Primary Water (MRP-188)
Technical Report
·
Mon Nov 01 00:00:00 EST 2004
·
OSTI ID:860571
+1 more
Characterization of Decommissioned PWR Vessel Internals Material Samples: Tensile and SSRT Testing (Nonproprietary Version)
Technical Report
·
Wed Sep 01 00:00:00 EDT 2004
·
OSTI ID:860571
Materials Reliability Program: Environmental Fatigue Testing of Type 304L Stainless Steel U-Bends in Simulated PWR Primary Water (MRP-188)
Technical Report
·
Tue Feb 28 00:00:00 EST 2006
·
OSTI ID:860571