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Division Spotlight
Materials Science & Technology
The objectives of MSTD are: promote the advancement of materials science in Nuclear Science Technology; support the multidisciplines which constitute it; encourage research by providing a forum for the presentation, exchange, and documentation of relevant information; promote the interaction and communication among its members; and recognize and reward its members for significant contributions to the field of materials science in nuclear technology.
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
June 2025
Nuclear Technology
Fusion Science and Technology
May 2025
Latest News
Industry Update—May 2025
Here is a recap of industry happenings from the recent past:
TerraPower’s Natrium reactor advances on several fronts
TerraPower has continued making aggressive progress in several areas for its under-construction Natrium Reactor Demonstration Project since the beginning of the year. Natrium is an advanced 345-MWe reactor that has liquid sodium as a coolant, improved fuel utilization, enhanced safety features, and an integrated energy storage system, allowing for a brief power output boost to 500-MWe if needed for grid resiliency. The company broke ground for its first Natrium plant in 2024 near a retiring coal plant in Kemmerer, Wyo.
Corinne Bangil, Gérard Gambier, Michel Soldevila
Nuclear Technology | Volume 84 | Number 3 | March 1989 | Pages 344-349
Technical Paper | Probabilistic Safety Assessment and Risk Management / Fuel Cycle | doi.org/10.13182/NT89-A34218
Articles are hosted by Taylor and Francis Online.
Pressurized water reactor four-batch fuel management represents, in the present context, an economic optimum for the French standardized series of reactors. Plutonium recycling on an industrial scale has already started in France; therefore, it is essential to ascertain its compatibility with four-batch refueling requirements. In the survey considered, it is shown that a core refueled annually with 28 UO2 assemblies, having a 3.7% 235 U content and 12 mixed-oxide assemblies containing 6.5% plutonium, entirely satisfies safety criteria under normal operating conditions. A supplementary survey will be performed to assess its behavior under such accident conditions as steam line break and rod ejection.