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Operations & Power
Members focus on the dissemination of knowledge and information in the area of power reactors with particular application to the production of electric power and process heat. The division sponsors meetings on the coverage of applied nuclear science and engineering as related to power plants, non-power reactors, and other nuclear facilities. It encourages and assists with the dissemination of knowledge pertinent to the safe and efficient operation of nuclear facilities through professional staff development, information exchange, and supporting the generation of viable solutions to current issues.
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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.”
Chan-Hyeong Kim, Siyoung Jang, Warren Dan Reece
Nuclear Technology | Volume 145 | Number 1 | January 2004 | Pages 1-10
Technical Paper | Fission Reactors | doi.org/10.13182/NT04-A3455
Articles are hosted by Taylor and Francis Online.
The Monte Carlo N-Particle (MCNP) code and a set of high-temperature neutron cross-section data were used to develop an accurate three-dimensional computational model of the Texas A&M University Nuclear Science Center Reactor (NSCR) at full power. The geometry of the reactor core was modeled as closely as possible including the details of all the fuel elements and control rods. The most significant approximation was made for entrained fission products because of the lack of knowledge of fission product inventory in the current reactor core. This study used the concept of "average fission product" to model the fission product in the reactor core and determined the concentration of the average fission product by repeating criticality calculations to make the reactor critical for a given critical condition. Finally, the developed model was tested by comparing the calculated results with those of other approaches, i.e., (a) an in-house three-dimensional diffusion code and (b) foil activation measurement. The developed reactor model showed a good agreement with these approaches. The developed model predicted the thermal neutron flux in samples within 11% of difference when compared with the results from the diffusion code and predicted the production of 198Au and 60Co within ~20% of difference when compared with the values measured with foils. The developed model also calculated the neutron energy spectrum very consistently with the other approaches for the entire energy range considered in this study.