Irradiation Effects on Reactor Structural Materials.
Abstract
The report, covering research for the period 1 November 1972 - 31 January 1973, includes: (1) postirradiation notch ductility assessments of austenitic stainless steel weldments, (2) studies of fatigue resistance of neutron irradiated cold worked Type 304 stainless steel, (3) environmental exposure studies of candidate first-wall materials in the Princeton ST Tokamak, (4) observations of bubble growth in 216 stainless steel implanted with helium, and (5) helium-Microstructure interaction in cyclotron-implanted, annealed, and cold-worked 316 stainless steel. (Author Modified Abstract)
Document Details
- Document Type
- Technical Report
- Publication Date
- Feb 15, 1973
- Accession Number
- AD0758355
Entities
People
- Lendell E. Steele
Organizations
- United States Naval Research Laboratory