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Members are devoted to applying nuclear science and engineering technologies involving isotopes, radiation applications, and associated equipment in scientific research, development, and industrial processes. Their interests lie primarily in education, industrial uses, biology, medicine, and health physics. Division committees include Analytical Applications of Isotopes and Radiation, Biology and Medicine, Radiation Applications, Radiation Sources and Detection, and Thermal Power Sources.
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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.”
Efigenio Cubillos-Moreno, Mohamed Belhadj, Tunc Aldemir
Nuclear Technology | Volume 98 | Number 3 | June 1992 | Pages 333-348
Technical Paper | Heat Transfer and Fluid Flow | doi.org/10.13182/NT92-A34663
Articles are hosted by Taylor and Francis Online.
The heat flux that leads to onset of nucleate boiling qONB is an important quantity for plate-type research reactors since it is frequently used as a thermal design constraint and also indicates the transition point from single- to two-phase heat removal in transient analyses. Recent experimental work has shown that qONB can be sensitive to both channel gap size d and flow velocity v under laminar, upward flow conditions that are encountered in such reactors under naturalconvection core cooling. New experimental data are presented to test the validity of the correlation proposed from the results of the previous work in extended d and local pressure p ranges. The correlation predicts the new experimental data for mixed or pure buoyancy-driven upward flows in 2.0 ≤ d ≤ 5.0 mm channels with 0.03 ≤ v ≤ 0.16 m/s and 1.05 × 105 ≤ p ≤ 1.70 × 105 Pa within 25%. The new d range covers almost all the existing and planned plate-type research reactors. The p range extends the applicability of the correlation to the analysis of a number of accident scenarios in open-pool reactors with power levels up to 5 to 10 MW, such as partial loss of pool water or coolant pump trip. The pressure range is also relevant to the analysis of similar accidents in higher power pressurized systems if the accident is accompanied by system depressurization. In the implementation of the correlation for such analyses, it is important to note that the correlation implicitly assumes that the wall superheat is nonnegative.