Accession Number : AD0698275

Title :   Irradiation Effects on Reactor Structural Materials.

Descriptive Note : Quarterly progress rept. 1 Aug-31 Oct 69,

Corporate Author : NAVAL RESEARCH LAB WASHINGTON D C

Personal Author(s) : Steele,L. E. ; Hawthorne,J. R. ; Watson,H. E. ; Serpan,C. Z. , Jr. ; Gray,R. A. , Jr

Report Date : 15 NOV 1969

Pagination or Media Count : 27

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)

Descriptors :   (*REACTOR MATERIALS, STEEL), (*STEEL, *DAMAGE), PRESSURE VESSELS, FRACTURE(MECHANICS), EMBRITTLEMENT, ANNEALING, THERMAL STABILITY, STAINLESS STEEL, DUCTILITY, SENSITIVITY, (U)SENSITIVITY

Subject Categories : Metallurgy and Metallography
      Radioactiv, Radioactive Wastes & Fission Prod

Distribution Statement : APPROVED FOR PUBLIC RELEASE