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ANS Student Conference 2025
April 3–5, 2025
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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.”
Adel Alapour, Robert A. Hommerson
Nuclear Technology | Volume 70 | Number 1 | July 1985 | Pages 64-73
Technical Paper | Third International Retran Meeting / Heat Transfer and Fluid Flow | doi.org/10.13182/NT85-A33664
Articles are hosted by Taylor and Francis Online.
A dual recirculation pump trip (2-RPT) test, conducted as a part of the Edwin I. Hatch Nuclear Plant Unit 2 (Hatch-2) startup testing, is analyzed using onedimensional reactor kinetics and point reactor kinetics options in RETRAN-02 MOD002. The nuclear data utilized in RETRAN are obtained by SIMTRAN using the three-dimensional core simulator solution by SIMULATE (RTS/7), taking into account exposure and the steady-state core conditions prior to the test. Scram does not occur during this test despite the actual sensed water level rise of ∼43 cm (water level had initially been lowered), while core power, flow, and pressure continue dropping until the natural circulation establishes a new equilibrium condition at a lower reactor power level. A combined interaction of system components is taken into account in the analysis by interfacing a detailed hydraulic model of the system, with control system models for feedwater flow and steam line pressure regulation using actual plant settings. Analysis of the actual data recorded during the 2-RPT test indicates good agreement between measured and calculated parameters. It is also demonstrated that in spite of rather large changes in the axial power distribution with time, as predicted by onedimensional reactor kinetics compared with that of the point kinetics model, a good overall agreement is reached.