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Division Spotlight
Nuclear Nonproliferation Policy
The mission of the Nuclear Nonproliferation Policy Division (NNPD) is to promote the peaceful use of nuclear technology while simultaneously preventing the diversion and misuse of nuclear material and technology through appropriate safeguards and security, and promotion of nuclear nonproliferation policies. To achieve this mission, the objectives of the NNPD are to: Promote policy that discourages the proliferation of nuclear technology and material to inappropriate entities. Provide information to ANS members, the technical community at large, opinion leaders, and decision makers to improve their understanding of nuclear nonproliferation issues. Become a recognized technical resource on nuclear nonproliferation, safeguards, and security issues. Serve as the integration and coordination body for nuclear nonproliferation activities for the ANS. Work cooperatively with other ANS divisions to achieve these objective nonproliferation policies.
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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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.
Yoshiyuki Asaoka, Kunihiko Okano, Tomoaki Yoshida, Ken Tomabechi, Yuichi Ogawa, Naoto Sekimura, Yuzo Fukai, Akiyoshi Hatayama, Nobuyuki Inoue, Akira Kohyama, Sei-Ichiro Yamazaki, Seiji Mori
Fusion Science and Technology | Volume 34 | Number 3 | November 1998 | Pages 863-867
Fusion Blanket and Shield Technology (Poster Session) | doi.org/10.13182/FST98-A11963720
Articles are hosted by Taylor and Francis Online.
The possibility of developing a cost competitive fusion power plant with a water-cooled blanket concept, which has much experience in nuclear power plants, was examined. The new blanket design is based on using reduced activation ferritic steel components and an advanced super-heated steam cycle which is used to realize high thermal efficiency. The high value of thermal efficiency is very effective in reducing the cost of electricity.
The allowable temperature range of the structure material, reduced activation ferritic steel, is assumed to be 350K to 900K based on expectations from the material research and development program. A mixture of lithium oxide pebbles and beryllium pebbles is installed in the breeding zone for high tritium breeding ratio and high thermal conductivity. Mixture ratio of beryllium and lithium-6 enrichment were optimized from the viewpoint of temperature distribution in the breeding zone, achievable tritium breeding ratio and its reduction due to burn up. The reference blanket system has a local tritium breeding ratio of 1.37. The arrangement of cooling channels in the breeding zones and flow rate and inlet temperature of the coolant were also optimized to keep the temperatures of structure materials, breeding materials and coolant in the allowable range. The first wall is cooled by pressurized water at about 570 K. The coolant out of the first wall is led to the breeding zone and starts to boil. The steam is super-heated up to 750 K in the blanket. This high temperature raises the thermal efficiency of the turbine to 41 %.