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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.”
J. D. Galambos, Y-K. M. Peng, L. J. Perkins
Fusion Science and Technology | Volume 19 | Number 3 | May 1991 | Pages 1463-1468
ITER | Proceedings of the Ninth Topical Meeting on the Technology of Fusion Energy (Oak Brook, Illinois, October 7-11, 1990) | doi.org/10.13182/FST91-A29547
Articles are hosted by Taylor and Francis Online.
The nominal International Thermonuclear Experimental Reactor (ITER) configuration is a double-null (DN) divertor, which requires precise plasma vertical position control. Vertical displacements of only about 1 cm (out of a plasma height of 4.7 m) are estimated to destroy the up/down symmetric distribution of power flow to the divertor plates. As an alternate configuration to avoid this difficulty, we look at the single-null (SN) option, where all the charged power flow is deposited on the lower divertor plate. The primary consideration in this study is that of technology phase performance (maximum neutron wall load) for the ITER divertor heat load and plasma constraints. With regard to the divertor heat loads, the SN case has the advantages of (a) longer scrape-off field line connection lengths and (b) more vertical space, which allows a greater spreading of the heat load on the divertor plates. These advantages offset the SN case disadvantage of having fewer divertor plates, and therefore the potential for higher heat fluxes for a given core plasma condition. The attainable wall loads for the SN and DN divertors are found to be similar for steady-state and hybrid operation scenarios.