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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.”
Ying T. Lee, Myron A. Hoffman, M. Hafez
Fusion Science and Technology | Volume 30 | Number 3 | December 1996 | Pages 669-673
Divertor Design and Experiments | doi.org/10.13182/FST96-A11963013
Articles are hosted by Taylor and Francis Online.
A subcooled nucleate boiling computer code (with 3D heat conduction in solid and 1D forced convection in fluid) that incorporates a good estimation of the single-phase and two-phase pressure drop was developed to evaluate a monoblock design of the divertor with smooth tubes as well as a wide variety of cooling designs. Using one of the monoblock divertor designs proposed by the European International Thermonuclear Experimental Reactor (ITER) team as of March 1995, it was found that under a normal steady state operating condition with a peak heat flux of about 5 MW/m2, the water flow remained in the single phase liquid regime. Under an abnormal operating condition with a peak heat flux of about 20 MW/m2, the partially developed boiling (PDB) regime occurred where the local critical heat flux safety factor, (SFCHF=CHF(z)/q“(0=0°)), was estimated to be about 1.4 using the Tong-75 CHF correlation. This indicates that further increases in the magnitude of the heat flux beyond 20 MW/m2 may raise safety concerns for the design. By increasing the mass flux, decreasing the inlet water temperature, or increasing the inlet water pressure, the CHF safety margin of the design can be increased without inserting twisted tapes inside cooling tubes.