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Division Spotlight
Isotopes & Radiation
Members are devoted to applying nuclear science and engineering technologies involving isotopes, radiation applications, and associated equipment in scientific research, development, and industrial processes. Their interests lie primarily in education, industrial uses, biology, medicine, and health physics. Division committees include Analytical Applications of Isotopes and Radiation, Biology and Medicine, Radiation Applications, Radiation Sources and Detection, and Thermal Power Sources.
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
May 2025
Nuclear Technology
Fusion Science and Technology
Latest News
TerraPower begins U.K. regulatory approval process
Seattle-based TerraPower signaled its interest this week in building its Natrium small modular reactor in the United Kingdom, the company announced.
TerraPower sent a letter to the U.K.’s Department for Energy Security and Net Zero, formally establishing its intention to enter the U.K. generic design assessment (GDA) process. This is TerraPower’s first step in deployment of its Natrium technology—a 345-MW sodium fast reactor coupled with a molten salt energy storage unit—on the international stage.
Hosny M. Attaya, Mohamed E. Sawan
Fusion Science and Technology | Volume 8 | Number 1 | July 1985 | Pages 608-613
Blanket and First-Wall Engineering | Proceedings of the Sixth Topical Meeting on the Technology of Fusion Energy (San Francisco, California, March 3-7, 1985) | doi.org/10.13182/FST85-A40106
Articles are hosted by Taylor and Francis Online.
A computer program for evaluating the poloidal distribution of the neutron wall loading (NWL) in toroidal fusion reactors is developed using numerical integration for general plasma and wall shapes. The neutron source within the plasma could be uniform or could be described to properly represent the neutron density associated with the magnetic flux surfaces. The method and techniques used in NEWLIT are presented. A comparison with the Monte-Carlo code MCNP shows excellent agreement with substantial savings in computer time and required user time. To verify the validity of the NWL as calculated by NEWLIT, a detailed 3-D neutronics calculation was carried out for a representative tokamak reactor. The poloidal distribution of the important responses is compared to the NWL poloidal distribution.