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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.”
Martin J. R. Pierre, Hugues W. Bonin
Nuclear Technology | Volume 125 | Number 1 | January 1999 | Pages 1-12
Technical Paper | Fission Reactors | doi.org/10.13182/NT99-A2928
Articles are hosted by Taylor and Francis Online.
The availability of the Monte Carlo-based code MCNP 4A has made possible the simulation of the low-enriched uranium (LEU)-fueled SLOWPOKE-2 reactor using a probabilistic approach. The reactor core and its surrounding pool can be modeled in three dimensions with numerous details included in the representation. Significant improvement from previous modeling attempts was obtained with the MCNP 4A simulation, with the discrepancy between the calculated and experimental values of the excess reactivity at 20°C reduced to only 0.2 mk. The analysis suggests the error of the MCNP 4A-calculated excess reactivity as between 1 and 2 mk.The SLOWPOKE-2 reactor was then simulated with its single control rod at various degrees of insertion in the core: The reactivity worth of the rod was calculated as 7.85 mk, only 2.4 mk above the measured value. MCNP was then used for predicting the temperature effects on the excess reactivity. Although the inherent safety of the SLOWPOKE-2 reactor was confirmed in the simulation, the temperature dependence of the excess reactivity could not however be accurately predicted, due for the most part to the lack of appropriate cross-section libraries available at the time of this work. The potential of MCNP 4A is nevertheless clearly demonstrated for the simulation of the LEU-fueled SLOWPOKE-2 reactor, once the missing cross sections become available for the low temperatures at which the reactor operates.