Irradiation Effects on Reactor Structural Materials.
Abstract
The report includes: (1) initial comparisons between dynamic tear test and Charpy V-notch impact data for irradiated steels, including the PM-2A vessel steel, (2) the recovery of ductility by annealing heat treatment of steels irradiated to different ratios of thermal to fast neutrons, (3) the unirradiated properties of special A533-B steel heat procured for low enbrittlement sensitivity, (4) data describing the thermal stability of a potential advanced reactor structural alloy, 5Ni-Cr-Mo-V steel, and (5) initial strength and ductility data on selected austenitic stainless steels, 304, 304L, 316, and 316L, after irradiation in the EBR-II reactor to fluences between 0.4 and 9.0 x 10 to the 20th power n/sq cm > 1 MeV at temperatures ranging from 700F (371C) to 830F (443C). (Author)
Document Details
- Document Type
- Technical Report
- Publication Date
- Nov 15, 1969
- Accession Number
- AD0698275
Entities
People
- C. Z. Serpan Jr.
- Henry E. Watson
- J. Russell Hawthorne
- Lendell E. Steele
- R. A. Gray Jr.
Organizations
- United States Naval Research Laboratory