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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
2024 ANS Winter Conference and Expo
November 17–21, 2024
Orlando, FL|Renaissance Orlando at SeaWorld
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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Latest News
National awards presented at ANS Winter Conference
One of the few constants at American Nuclear Society national meetings is the recognition of exceptional individuals in the nuclear community. ANS President Lisa Marshall has named this season’s award recipients, who received recognition at this week's Winter Conference and Expo in Orlando, Fla.
ANS also announced the winners of awards presented by the Society’s professional divisions. These awards have been mailed to the recipients, and the divisions have recognized or will recognize honorees at various division functions and meetings this fall. The 19 professional divisions of ANS are constituent units and represent a vast array of nuclear science and technology disciplines.
Hisashi Ninokata, Hideki Kamide
Nuclear Technology | Volume 181 | Number 1 | January 2013 | Pages 11-23
Technical Paper | Special Issue on the 14th International Topical Meeting on Nuclear Reactor Thermal Hydraulics (NURETH-14) / Fission Reactors; Thermal Hydraulics | doi.org/10.13182/NT13-A15753
Articles are hosted by Taylor and Francis Online.
This paper discusses key issues and highlighted topics in thermal hydraulics in connection with Japan's current sodium-cooled fast reactor development efforts, with particular focus on design study and related research of the Japan Sodium-Cooled Fast Reactor (JSFR). Several innovative technologies, i.e., compact reactor vessel, two-loop system, full natural-circulation decay heat removal, and recriticality-free core, have been investigated to reduce construction cost and to achieve a high level of reactor safety. Preliminary evaluations of innovative technologies to be applied to JSFR are ongoing. In this paper, the progress of design study is reviewed, and key issues are discussed. Then, research and development activities on the thermal hydraulics are highlighted in connection with the phenomena taking place in natural-circulation decay heat removal and innovative design and enhanced safety features.