ANS is committed to advancing, fostering, and promoting the development and application of nuclear sciences and technologies to benefit society.
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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.
E. Lin, Y. H. Cheng, J. K. Hsiue
Nuclear Technology | Volume 54 | Number 3 | September 1981 | Pages 380-384
First International Retran Meeting | Heat Transfer and Fluid Flow | doi.org/10.13182/NT81-A32783
Articles are hosted by Taylor and Francis Online.
Full power generator load rejection transient initiated in startup test was simulated. The measured data are retrieved from STARTREC tape. The calculated and measured data especially for parameters of system pressure, core heat flux, feedwater flow rate, reactor water level, core flow, and normalized power are compared. The results indicate that the RETRAN code can successfully predict the parameters.
