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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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Nuclear Science and Engineering
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Nuclear Technology
April 2025
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Latest News
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.”
Samir M. Sami, C. H. Le
Nuclear Technology | Volume 77 | Number 1 | April 1987 | Pages 7-17
Technical Paper | Fission Reactor | doi.org/10.13182/NT87-A33947
Articles are hosted by Taylor and Francis Online.
A dynamic void quality perturbation model has been developed to improve the capabilities of the NUFREQ code with respect to local void perturbation calculations. The present model calculates the local void perturbation in terms of the local quality perturbation, the dynamic drift flux parameters, and the transient time. In addition, the model evaluates the void reactivity feedback and the boiling channel nuclear reactor feedback. Depending on the flow regime, this model can predict the local void fraction perturbation in horizontal (CANDU reactors) and vertical channels (light water reactors). Numerical results revealed that this model enhanced the capabilities of the NUFREQ code and improved its accuracy in predicting the lower natural frequency as well as the system frequency response at higher frequencies.
