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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.”
Kiyoshi Yatsu, Leonid G. Bruskin, Teruji Cho, Minoru Hamada, Mafumi Hirata, Hitoshi Hojo, Makoto Ichimura, Kameo Ishii, Khairul M. Islam, Akiyoshi Itakura, Isao Katanuma, Yasuhito Kiwamoto, Junko Kohagura, Shigeyuki Kubota, Atsushi Mase, Yousuke Nakashima, Teruo Saito, Yoshiteru Sakamoto, Teruo Tamano, Yoshinori Tatematsu, Tokihiko Tokuzawa, Masayuki Yoshikawa
Fusion Science and Technology | Volume 35 | Number 1 | January 1999 | Pages 52-59
Invited Lectures | doi.org/10.13182/FST99-A11963826
Articles are hosted by Taylor and Francis Online.
Potential confinement of an ICRF-heated high-ion temperature plasma in GAMMA 10 is experimentally studied. The potential confinement was shown from data of one-end plugging and both-end plugging. The waveform of end loss current and an analysis of end loss ion energies have also indicated potential formation and confinement. The central cell line density increases 50% by the potential confinement. Some radial losses were observed in the anchor and/or plug/barrier regions and a rate of the radial loss was measured by using the data from one-end plugging. Under an experimental condition, the radial loss rate was estimated to be about 3%. In order to reduce the radial loss, conducting plates were installed adjacent to the plasma in the anchor transition region. The density increase of 60 % was attained after installation of the conducting plates and a higher density increase can be expected in the near future. The density increase was 50% before installation of the conducting plates. Controllability and reproducibility of the potential confinement are also improved after installation of the conducting plates.