About ANS
- ANS is committed to advancing, fostering, and promoting the development and application of nuclear sciences and technologies to benefit society.
About Nuclear
- Explore the many uses for nuclear science and its impact on energy, the environment, healthcare, food, and more.
Communities
- 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.
Events
- 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
- 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!
Publications
- Latest Magazine Issues
  Apr 2025
  Jan 2025
  Latest Journal Issues
  Nuclear Science and Engineering
  May 2025
  Nuclear Technology
  May 2025
  Fusion Science and Technology
  April 2025
- Latest News
  Ontario Power Generation issues license to build an SMR at Darlington
  The Canadian Nuclear Safety Commission has announced its approval for Ontario Power Generation to construct a General Electric Hitachi BWRX-300 small modular reactor at its Darlington site in Clarington, Ontario.
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Development of a Numerical Framework to Model Flow Accelerated Corrosion in a Lead Loop

Khaled Talaat, Rubel Das, Brian Romero, Cemal Cakez, Osman Anderoglu, Sang Lee (Univ of New Mexico), Youho Lee (Seoul Natl Univ), Heng Ban (Univ of Pittsburgh), Keith Woloshun, Seung Jun Kim, Dasari Rao, Cetin Unal (LANL)

Proceedings | 18th International Topical Meeting on Nuclear Reactor Thermal Hydraulics (NURETH 2019) | Portland, OR, August 18-23 | Pages 1360-1370