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The Radiation Protection and Shielding Division is developing and promoting radiation protection and shielding aspects of nuclear science and technology — including interaction of nuclear radiation with materials and biological systems, instruments and techniques for the measurement of nuclear radiation fields, and radiation shield design and evaluation.
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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.”
Paul E. Murray
Nuclear Technology | Volume 100 | Number 1 | October 1992 | Pages 135-140
Technical Note | Heat Transfer and Fluid Flow | doi.org/10.13182/NT92-A34759
Articles are hosted by Taylor and Francis Online.
The numerical solution of heat transfer problems may involve substantial execution time, and much of the execution time may be spent in the matrix solver. Iterative solution methods may be more efficient than direct methods for solving a large matrix equation. Although iterative methods have been applied to many fields of engineering simulation, they are not widely used in nuclear reactor simulation. Moreover, the selection of a suitable iterative method depends on the problem. Heat transfer in nuclear reactors is a complex process that includes solid conduction, fluid advection, radiation, and convection between solid and fluid. Thus, the feasibility of matrix iterative solution methods is investigated, and the numerical performance of a selected iterative method is assessed. The preconditioned generalized conjugate residual (PGCR) method is an iterative method used in the integrated systems code (ISC) to simulate heat transfer in a modular high-temperature gas-cooled reactor. The numerical performance of the PGCR method is assessed to determine the computational requirements of the ISC. A steady-state heat transfer problem that includes conduction, convection, advection, and radiation heat transfer is solved in the performance study. The execution time of the PGCR method is obtained in the cases of four matrix sizes and three values of the heat transfer Biot number. The Biot number is varied to examine a complete range of convective heat transfer conditions. The execution time per equation is 0.22 to 0.55 ms on the Cray X-MP and 1.6 to 5.0 ms on the Dec 5000 workstation. These results show that the PGCR method is effective for nuclear reactor heat transfer calculations and provides an efficient and reliable computational performance.