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Division Spotlight
Mathematics & Computation
Division members promote the advancement of mathematical and computational methods for solving problems arising in all disciplines encompassed by the Society. They place particular emphasis on numerical techniques for efficient computer applications to aid in the dissemination, integration, and proper use of computer codes, including preparation of computational benchmark and development of standards for computing practices, and to encourage the development on new computer codes and broaden their use.
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.
Dave Knott, Erin Wehlage
Nuclear Science and Engineering | Volume 155 | Number 3 | March 2007 | Pages 331-354
Technical Paper | Mathematics and Computation, Supercomputing, Reactor Physics and Nuclear and Biological Applications | doi.org/10.13182/NSE155-331
Articles are hosted by Taylor and Francis Online.
This paper presents a description of the lattice physics code LANCER02, developed for use on boiling water reactor fuel designs at Global Nuclear Fuel and General Electric Energy, Nuclear. Included in the paper is a detailed description of the methodology used to determine the neutron flux distribution throughout the problem. The paper focuses on single-assembly analysis as well as multibundle analysis along a plane of a reactor core. A small sampling of results from the lattice physics code are compared against results generated by continuous-energy Monte Carlo analysis.