The NRL-EPRI Research Program (RP886-2) Evaluation and Prediction of Neutron Embrittlement in Reactor Pressure Vessel Materials.
Annual progress rept. for CY 1977,
NAVAL RESEARCH LAB WASHINGTON D C
Pagination or Media Count:
Nuclear reactor pressure vessel materials are subject to progressive reductions in fracture resistance in service due to neutron irradiation. Current technology is insufficient to quantitatively predict radiation embrittlement for all typical materials and their metallurgical variations for neutron fluences of interest. Another needed refinement to radiation effects technology involves the establishment of a relationship between apparent notch ductility and fracture toughness in the irradiated condition. The current program was formulated to advance both areas for the benefit of reactor vessel design and operation. An immediate objective involves the development of a high quality data base for the evaluation of current radiation embrittlement projection methods and the development of improved methods.
- Metallurgy and Metallography
- Fission Reactor Materials