Irradiation Effects on Reactor Structural Materials.
Abstract
The report includes: (1) effect of hold-time on fatigue crack propagation in thermally aged, annealed and 25% cold-worked 304 stainless steel; (2) notch ductility retention of A543 submerged arc and electroslag weld deposits after irradiation; (3) temperature and dose rate dependence of void nucleation and growth in heavy ion bombarded nickel; (4) studies of the mobility of helium in vanadium; (5) effect of cyclotron-implanted helium on the fatigue behavior of 316 stainless steel; and (6) notch toughness of irradiated 316 stainless steel weld. (Modified author abstract)
Document Details
- Document Type
- Technical Report
- Publication Date
- Mar 01, 1974
- Accession Number
- AD0777433
Entities
People
- Lendell E. Steele
Organizations
- United States Naval Research Laboratory