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Radiation Protection & Shielding
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
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.”
Satish Kumar Dhurandhar, S. L. Sinha, Shashi Kant Verma
Nuclear Technology | Volume 206 | Number 5 | May 2020 | Pages 663-696
Critical Review | doi.org/10.1080/00295450.2019.1698257
Articles are hosted by Taylor and Francis Online.
Flow and thermal performance analysis is an important area in the nuclear industry for the safe operation of reactors and the optimum design of fuel rod bundles with spacers in the reactor core. The spacer, an essential element in the nuclear fuel rod assembly, is used to support the fuel rods in the bundle and maintain suitable clearance between the rods. This paper represents a comprehensive review of the effects of spacer/mixing vane spacer on flow behavior and heat transfer performance in nuclear fuel rod bundles, annular channels, and circular tubes. This paper is based on the experimental and computational fluid dynamics (CFD) investigations performed by researchers in literature for both single-phase and two-phase fluid flow. In addition, the effects of some parameters, such as Reynolds number, hydraulic diameter, pitch-to-diameter ratio, blockage ratio, working fluid, and number of fuel rods in an assembly, on flow and thermal performance analysis have been reviewed. A detailed review has been carried out by considering both experimental and CFD methods used in the past for analysis of thermal-hydraulic performance in the fuel channels of nuclear reactors.