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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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June 2025
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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.
A. Cihat Baytaṣ
Nuclear Technology | Volume 90 | Number 3 | June 1990 | Pages 417-425
Technical Paper | RELAP/MOD2 / Heat Transfer and fluid Flow | doi.org/10.13182/NT90-A34405
Articles are hosted by Taylor and Francis Online.
Many computer codes are based on subchannel analysis, which is important for thermal-hydraulic analysis of the reactor core. Most of these codes make some assumptions to determine the axial velocity in the gap region (AVGR), but no real arguments have been given to justify these assumptions. A new way to determine the AVGR between two parallel single-phase flows that communicate by a lateral slot has been successfully incorporated in Tapucu’s subchannel analysis experiments.