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General Kenneth Nichols and the Manhattan Project
Nichols
The Oak Ridger has published the latest in a series of articles about General Kenneth D. Nichols, the Manhattan Project, and the 1954 Atomic Energy Act. The series has been produced by Nichols’ grandniece Barbara Rogers Scollin and Oak Ridge (Tenn.) city historian David Ray Smith. Gen. Nichols (1907–2000) was the district engineer for the Manhattan Engineer District during the Manhattan Project.
As Smith and Scollin explain, Nichols “had supervision of the research and development connected with, and the design, construction, and operation of, all plants required to produce plutonium-239 and uranium-235, including the construction of the towns of Oak Ridge, Tennessee, and Richland, Washington. The responsibility of his position was massive as he oversaw a workforce of both military and civilian personnel of approximately 125,000; his Oak Ridge office became the center of the wartime atomic energy’s activities.”
M. R. Fox, A. B. Hull, T. F. Kassner
Fusion Science and Technology | Volume 19 | Number 3 | May 1991 | Pages 1619-1628
Material and Tritium | Proceedings of the Ninth Topical Meeting on the Technology of Fusion Energy (Oak Brook, Illinois, October 7-11, 1990) | doi.org/10.13182/FST91-A29573
Articles are hosted by Taylor and Francis Online.
Susceptibility of Types 316NG, 316, and 304 stainless steels (SS) to stress corrosion cracking was investigated in slow-strain-rate tests (SSRTs) in oxygenated water that simulates important parameters anticipated in first-wall/blanket systems. The water chemistry was based on a computer code that yielded the nominal concentrations of radiolytic species produced in an aqueous environment under conditions expected in the International Thermonuclear Experimental Reactor (ITER). Actual SSRTs were performed in a less benign, more oxidizing reference environment at temperatures of 52 to 150°C. Predominantly ductile fracture was observed in Type 316NG and nonsensitized Types 316 and 304 SS SSRT specimens that were strained to failure in a reference ITER water chemistry. The failure behavior of Type 304 SS specimens, heat-treated to yield sensitization values of 2, 3, and 20 Coulomb (C)/cm2 by the electrochemical potentiokinetic reactivation technique, demonstrated that the degree of sensitization dramatically affected susceptibility to intergranular stress corrosion cracking. Ranking for resistance to stress corrosion cracking in simulated ITER water by electron microscopy and SSRT parameters, i.e., failure time, ultimate strength, total elongation, and stress ratio, is 304 SS (EPR = 20<2 C/cm2)<316NG SS.