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Division Spotlight
Nuclear Criticality Safety
NCSD provides communication among nuclear criticality safety professionals through the development of standards, the evolution of training methods and materials, the presentation of technical data and procedures, and the creation of specialty publications. In these ways, the division furthers the exchange of technical information on nuclear criticality safety with the ultimate goal of promoting the safe handling of fissionable materials outside reactors.
Meeting Spotlight
Utility Working Conference and Vendor Technology Expo (UWC 2024)
August 4–7, 2024
Marco Island, FL|JW Marriott Marco Island
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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August 2024
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Latest News
NRC engineers share their expertise at the University of Puerto Rico
Robert Roche-Rivera and Marcos Rolón-Acevedo are licensed professional engineers who work at the U.S. Nuclear Regulatory Commission. They are also alumni of the University of Puerto Rico–Mayagüez (UPRM) and have been sharing their knowledge and experience with students at their alma mater since last year, serving as adjunct professors in the university’s Department of Mechanical Engineering. During the 2023–2024 school year, they each taught two courses: Fundamentals of Nuclear Science and Engineering, and Nuclear Power Plant Engineering.
Yasushi Nauchi, Tetsuo Matsumura
Nuclear Science and Engineering | Volume 196 | Number 11 | November 2022 | Pages 1306-1322
Technical Paper | doi.org/10.1080/00295639.2022.2092355
Articles are hosted by Taylor and Francis Online.
The γ-mode eigenvalue problem is investigated to utilize an exponential experiment to validate nuclear data for reactor core analyses. The perturbation of the spatial decay constant γ by the bias of nuclear data is analyzed with the adjoint flux of the γ-mode eigenvalue problem. The adjoint flux at a phase-space position is found to be proportional to the amplitude of the neutron flux on a plane vertically distant from a source placed at the position. The implication of the adjoint flux is numerically demonstrated based on the diffusion theory. The perturbation theory relating the bias of the fission neutron emission to the perturbation of γ is preliminarily justified in the manner of the continuous energy Monte Carlo.