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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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Nuclear Technology
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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.
James Corson, Alice Chung, Steven Muller
Nuclear Technology | Volume 210 | Number 2 | February 2024 | Pages 261-268
Research Article | doi.org/10.1080/00295450.2023.2181042
Articles are hosted by Taylor and Francis Online.
This paper presents the Fuel Analysis under Steady-state and Transient (FAST) code contribution to the P2M Simulation Exercise on past fuel melting irradiation experiments organized within the Organisation for Economic Co-operation and Development/Nuclear Energy Agency’s Framework for Irradiated Experiments (FIDES). The benchmark consists of comparisons to two power ramps (xM-3 and HBC-4) that experienced fuel centerline melting. In general, FAST accurately captured the behavior of the fuel rods during the tests, though there are some notable discrepancies between the FAST results and the cladding elongation and fission gas release during the xM-3 power ramp.
