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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.”
Ki-Yong Choi, Seok Cho, Hyoung-Kyu Cho, Chul-Hwa Song
Nuclear Technology | Volume 170 | Number 1 | April 2010 | Pages 54-67
Technical Paper | Special Issue on the 2008 International Congress on Advances in Nuclear Power Plants / Thermal Hydraulics | doi.org/10.13182/NT10-A9445
Articles are hosted by Taylor and Francis Online.
The 6 × 6 reflood test facility for Advanced Thermal Hydraulic Evaluation of Reflood phenomena (ATHER) has been operated by Korea Atomic Energy Research Institute to investigate the reflooding phenomena in a rod bundle. A series of bottom reflood tests was carried out by varying several parameters affecting the reflooding process such as the flooding velocity, inlet coolant subcooling, system pressure, initial maximum rod wall temperature, and rod power. Subsequently, counterpart reflood tests of rod bundle heat transfer data from The Pennsylvania State University were conducted for comparison, focusing especially on the effects of the heat flux on the peak cladding temperature (PCT) and the quenching behavior. The best-estimate thermal-hydraulic system analysis code MARS3.1 was assessed with the obtained data to investigate the parametric effects on its prediction accuracy. It was found that the prediction accuracy of the PCT is reasonable on the whole but that the MARS code predicts delayed quenching behavior compared with the data, especially for high heat flux conditions. In particular, the prediction becomes deteriorated downstream, far from the inlet of the test section.
