The NRL-EPRI Research Program (RP886-2), Evaluation and Prediction of Neutron Embrittlement in Reactor Pressure Vessel Materials.
Abstract
Nuclear reactor pressure vessel materials are subject to progressive reductions in fracture resistance in service due to neutron irradiation. Current technology is inadequate to quantitatively predict radiation embrittlement for all vessel materials and their metallurgical variations for the neutron fluences of interest. In addition a relationship between apparent notch ductility and fracture toughness in the irradiated condition is needed to evolve more quantitative projections of structural integrity. The NRL-EPRI RP886-2 Program was formulated to advance both areas for the benefit of reactor vessel design and operation. A primary objective is development of a high-quality data base for the evaluation of current radiation-embrittlement projection methods and the development of improved methods. This report documents program highlights and research results for CY 1978. Principal results include completion of half of the scheduled program irradiation experiments as well as commencement of postirradiation notch ductility and fracture toughness testing. The facility and procedures developed for J-R curve testing of irradiated compact toughness specimens are described. Postirradiation results are presented for four experiments which contained A533-B steel plate material.
Document Details
- Document Type
- Technical Report
- Publication Date
- Aug 30, 1979
- Accession Number
- ADA075012
Entities
People
- J. Russell Hawthorne
Organizations
- United States Naval Research Laboratory