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Division Spotlight
Thermal Hydraulics
The division provides a forum for focused technical dialogue on thermal hydraulic technology in the nuclear industry. Specifically, this will include heat transfer and fluid mechanics involved in the utilization of nuclear energy. It is intended to attract the highest quality of theoretical and experimental work to ANS, including research on basic phenomena and application to nuclear system design.
Meeting Spotlight
ANS Student Conference 2025
April 3–5, 2025
Albuquerque, NM|The University of New Mexico
Standards Program
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.”
Yasushi Nomura, Hiroshi Okuno
Nuclear Technology | Volume 109 | Number 1 | January 1995 | Pages 142-152
Technical Paper | Nuclear Criticality Safety | doi.org/10.13182/NT95-A35074
Articles are hosted by Taylor and Francis Online.
For handling of nuclear fuel during reprocessing or for design of spent-fuel storage and transportation, one needs to know the scale of maximum credible criticality accidents, i.e., the total fission number so as to know the radiological exposure of working personnel as well as the risk to the public in the event of an accident. Some simplified evaluation models for conservatively predicting the number of total fissions during an accident are derived theoretically using the one-point adiabatic reactivity balance model for the homogeneous and heterogeneous systems, respectively, which are frequently seen in nuclear fuel facilities. These simplified evaluation models are subsequently validated with the transient experiment data and actual accident data published to date from the world nuclear community. Some conventionally used simplified evaluation models of this kind are quoted and compared with the results to show the convenience of the current models, having almost no restrictions in the application for any kind of nuclear fuel, material composition, geometry, and dimension, and thus, ensuring adequate margins for predicting the total fission number at the time of a critsssicality accident.