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Reactor Physics
The division's objectives are to promote the advancement of knowledge and understanding of the fundamental physical phenomena characterizing nuclear reactors and other nuclear systems. The division encourages research and disseminates information through meetings and publications. Areas of technical interest include nuclear data, particle interactions and transport, reactor and nuclear systems analysis, methods, design, validation and operating experience and standards. The Wigner Award heads the awards program.
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ANS Student Conference 2025
April 3–5, 2025
Albuquerque, NM|The University of New Mexico
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The Standards Committee is responsible for the development and maintenance of voluntary consensus standards that address the design, analysis, and operation of components, systems, and facilities related to the application of nuclear science and technology. Find out What’s New, check out the Standards Store, or Get Involved today!
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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.”
Doron Gal, David Saphier, Ezra Elias
Nuclear Technology | Volume 95 | Number 1 | July 1991 | Pages 64-76
Technical Paper | Heat Transfer and Fluid Flow | doi.org/10.13182/NT91-A34568
Articles are hosted by Taylor and Francis Online.
A U-tube steam generator (UTSG) module for the Dynamic Simulator for Nuclear Power Plants is developed. This module is to be used in the simulation of pressurized water reactor (PWR) transients and parametric studies, and it is based on a movable boundary model in which the volumes of the various control volumes are dynamic variables. The UTSG is divided into ten control volumes with movable boundaries between them. The intensive mass and energy balance equations are solved in each control volume, while two integral momentum equations are solved for the primary and secondary flow paths. A homogeneous equilibrium model is assumed in the boiling region. The UTSG model was included in a detailed simulation of the Trojan PWR primary loop. A small loss-of-coolant accident event resulting from a stuck open relief valve transient is presented as an application example.
