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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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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.
Yi-Chiang Chang, Alexander Sesonske
Nuclear Technology | Volume 65 | Number 2 | May 1984 | Pages 292-304
Technical Paper | Fuel Cycle | doi.org/10.13182/NT84-A33412
Articles are hosted by Taylor and Francis Online.
Low-leakage extended burnup fuel management is a promising pressurized water reactor (PWR) improvement that yields better neutron economy than the traditional out-in fuel management scheme with resulting economic savings and a likely reduction in vessel fast neutron fluence. The Commonwealth Edison Zion-1 reactor was selected as representative of current operating PWRs and analyzed. A major objective was to develop and analyze optimum transition loading arrangements leading from present out-in management to the desired low-leakage scheme. A so-called “wet” burnable poison was used in the calcula-tional model, which was based on various Electric Power Research Institute/Advanced Recycle Methodology Program modules. An accelerated direct search scheme was developed to optimize the loading pattern utilizing the initial boron concentration as the objective function, which would correspond to a maximum cycle length for a given number of loaded fresh assemblies. The equilibrium cycle, with 32 of 48 fresh assemblies loaded in the core interior, resulted in a 6.4% saving in fuel cycle costs compared with a three-batch out-in strategy, and a 3.8% saving compared with a four-batch out-in strategy. Therefore, the low-leakage option is a promising improvement and detailed design is justified.