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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.”
L. Crosatti, D. L. Sadowski, S. I. Abdel-Khalik, M. Yoda, ARIES Team
Fusion Science and Technology | Volume 56 | Number 1 | July 2009 | Pages 96-100
Divertor and High Heat Flux Components | Eighteenth Topical Meeting on the Technology of Fusion Energy (Part 1) | doi.org/10.13182/FST09-A8883
Articles are hosted by Taylor and Francis Online.
Extensive experimental and numerical studies of the planar jet impingement concept used in gas-cooled T-tube divertor modules have been previously performed at Georgia Tech.1 The experiments were used to validate the numerical CFD model based on the FLUENT[registered] software package. However, the test module used in those experiments did not duplicate the exact geometry of the T-tube divertor, particularly the single-sided nature of the incident heat flux. In this paper, the thermal performance of a prototypical T-tube divertor module is experimentally and numerically examined. The test module has been designed and constructed to match the geometry, dimensions, material properties, and single-sided heating configuration of the actual T-tube divertor. Experiments were performed using air as the coolant with different values of the incident heat flux. The coolant flow rate and inlet pressure were selected to span the expected range of non-dimensional parameters for the actual helium-cooled T-tube divertor design. The experimental values of the local heat transfer coefficient and pressure drop show good agreement with the numerical (FLUENT[registered] 6.3) predictions. The data obtained in this investigation provide added confidence in the predicted performance of the T-tube divertor concept, and the ability of the FLUENT CFD software package to predict its thermal performance, as well as the thermal performance of other complex gas-cooled high heat flux components.