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Division Spotlight
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.
Meeting Spotlight
International Conference on Mathematics and Computational Methods Applied to Nuclear Science and Engineering (M&C 2025)
April 27–30, 2025
Denver, CO|The Westin Denver Downtown
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
June 2025
Nuclear Technology
May 2025
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Latest News
Sam Altman steps down as Oklo board chair
Advanced nuclear company Oklo Inc. has new leadership for its board of directors as billionaire Sam Altman is stepping down from the position he has held since 2015. The move is meant to open new partnership opportunities with OpenAI, where Altman is CEO, and other artificial intelligence companies.
H. Kumawat
Nuclear Science and Engineering | Volume 199 | Number 4 | April 2025 | Pages 550-556
Review Article | doi.org/10.1080/00295639.2024.2380636
Articles are hosted by Taylor and Francis Online.
The Monte Carlo Nucleon Transport (MONC) code for nucleon transport is extended for below 20-MeV proton transport using the ENDF and EXFOR databases. It is used to simulate the p + 7Li reaction up to 20-MeV proton energies, with the produced neutron spectra reported here. The simulated results are compared with the calculated values from other available codes like PINO, EPEN, and SimLiT, as well as experimental data. The spectra reported here can be used to get the neutron cross section for the quasi-monoenergetic neutron reaction and will help to subtract the low-energy contribution. The primary neutron spectra and its transport are useful, as this reaction has the potential for accelerator-based boron neutron capture therapy. The backing materials are used to fully stop the proton beam, hence the contributions of the neutrons from backing materials are estimated. It is found that tantalum is a good backing material below ~8 MeV and that carbon is better at higher energies.