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Division members promote the advancement of mathematical and computational methods for solving problems arising in all disciplines encompassed by the Society. They place particular emphasis on numerical techniques for efficient computer applications to aid in the dissemination, integration, and proper use of computer codes, including preparation of computational benchmark and development of standards for computing practices, and to encourage the development on new computer codes and broaden their use.
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2025 ANS Annual Conference
June 15–18, 2025
Chicago, IL|Chicago Marriott Downtown
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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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Fusion Science and Technology
Latest News
Webinar: MC&A and safety in advanced reactors in focus
Towell
Russell
Prasad
The American Nuclear Society’s Nuclear Nonproliferation Policy Division recently hosted a webinar on updating material control and accounting (MC&A) and security regulations for the evolving field of advanced reactors.
Moderator Shikha Prasad (CEO, Srijan LLC) was joined by two presenters, John Russell and Lester Towell, who looked at how regulations that were historically developed for traditional light water reactors will apply to the next generation of nuclear technology and what changes need to be made.
T. Nishitani, K. Kondo, S. Ohira, T. Yamanishi, M. Sugimoto, T. Hayashi, K. Ochiai
Fusion Science and Technology | Volume 68 | Number 2 | September 2015 | Pages 326-330
Technical Paper | Proceedings of TOFE-2014 | doi.org/10.13182/FST14-930
Articles are hosted by Taylor and Francis Online.
A neutron source for material and component tests is an essential tool for the DEMO reactor development. An accelerator-based neutron source such as IFMIF is regarded as the most promising one in Japan and the EU. The construction plan of IFMIF is still open due to the influence of the large cost overrun of ITER procurements. Japan Atomic Energy Agency (JAEA) has a plan of a neutron source for material and component tests using an IFMIF/EVEDA prototype accelerator and a lithium test loop for the IFMIF target facility. Expected performances of three options; 9 MeV and upgrading to 26 or 40 MeV of deuteron beam, are discussed. At the back plate position of the target, 1.5, 14, and 25 dpa/fpy are expected for 9, 26, and 40 MeV case, respectively. The option of 40 MeV is desirable, however, the option of 26 MeV is acceptable for blanket functional tests and material tests.