IRRADIATION EFFECTS ON REACTOR STRUCTURAL MATERIALS.
Abstract
The report includes the following: (1) a comparison of the response of selected structural steels to irradiation at 550 and 650F to high neutron fluences, (2) the through-thickness Charpy-V notch ductility performance of a 10-1/2-in.-thick plate of irradiated A302-B steel, (3) an investigation of the effects of oxygen and nitrogen contents on the radiation embrittlement sensitivity of 7-1/2Ni-Cr-Mo steel at 250F, (4) the notch ductility behavior of irradiated 12Ni-5Cr-3Mo maraging steel weldments, (5) the response of A350-LF1 (Modified) steel to postirradiation annealing at temperatures in the range of 550 to 590F, (6) the notch ductility behavior of A350-LF1 (Modified) steel with cyclic 430F irradiation-168 hour annealing, (7) the preirradiation mechanical properties of the MH-1A reactor pressure vessel steel, (8) the notch ductility of several reactor structural steels after irradiation in a heavy water moderated reactor, (9) the modification, installation, and initial operation of a remotely operated, tape-controlled milling machine, and (10) a description of newly acquired remotely operated precision measuring equipment. (Author)
Document Details
- Document Type
- Technical Report
- Publication Date
- May 15, 1967
- Accession Number
- AD0656578
Entities
People
- C. Z. Serpan Jr.
- Henry E. Watson
- J. Russell Hawthorne
- R. A. Gray Jr.
Organizations
- United States Naval Research Laboratory