Health and Safety Laboratory Fallout Program Quarterly Summary Report: December 1, 1973 - March 1, 1974 (open access)

Health and Safety Laboratory Fallout Program Quarterly Summary Report: December 1, 1973 - March 1, 1974

Report documenting radioactive fallout across the world, including both material in the atmosphere and that has deposited into food supplies.
Date: April 1, 1974
Creator: U.S. Atomic Energy Commission. Health and Safety Laboratory.
System: The UNT Digital Library
Health and Safety Laboratory Fallout Program Quarterly Summary Report: December 1, 1973 - March 1, 1974, Appendix (open access)

Health and Safety Laboratory Fallout Program Quarterly Summary Report: December 1, 1973 - March 1, 1974, Appendix

Report documenting radioactive fallout across the world, including both material in the atmosphere and that has deposited into food supplies. This appendix includes tables of monthly fallout deposition collections from 116 sites across the Earth and a list of radionuclides and their half-lives.
Date: April 1, 1974
Creator: U.S. Atomic Energy Commission. Health and Safety Laboratory.
System: The UNT Digital Library
A Survey of the Effects of Neutron Irradiation on the Impact and Other Mechanical Properties of Pressure Vessel Steels for the SM-2 Reactor (open access)

A Survey of the Effects of Neutron Irradiation on the Impact and Other Mechanical Properties of Pressure Vessel Steels for the SM-2 Reactor

Abstract: This technical report summarizes the data obtained in a recent literature survey conducted to determine the effects of neutron irradiation on the impact and other mechanical properties of both ferritic steels and austenitic stainless steels. The survey was primarily aimed at obtaining sufficient data on the behavior of pressure vessel steels at high integrated neutron flux levels in order that a reference material of construction could be selected for the SM-2 (APPR-1B) reactor vessel. Materials studied in this literature survey included carbon and low alloy steels such as: ASTM A-212B, ASTM A-201, ASTM A-301B (CR-Mo), ASTM A-106 (coarse and fine grained), ASTM A-285, ASTM A-302B (Mn-Mo), ASTM A-353, ASTM A-203 Grade D, E-7016 carbon steel weld metal, USS Carilloy T-1, HY-65 and HY-80. In addition, Types 304 and 347 stainless steels were also investigated as representative austenitic materials which might be used in pressure vessel construction. A careful evaluation was made of the irradiation induced changes in the mechanical properties of the above materials. The ferritic steels were evaluated primarily on the basis of increases in transition temperature due to irradiation and decreases in the amount of maximum energy absorbed prior to ductile failure. Factors such as industrial experience, …
Date: April 1, 1960
Creator: Kelleman, Richard William.
System: The UNT Digital Library