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
Thermal Hydraulics
The division provides a forum for focused technical dialogue on thermal hydraulic technology in the nuclear industry. Specifically, this will include heat transfer and fluid mechanics involved in the utilization of nuclear energy. It is intended to attract the highest quality of theoretical and experimental work to ANS, including research on basic phenomena and application to nuclear system design.
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.
A. W. Gray
Nuclear Technology | Volume 12 | Number 4 | December 1971 | Pages 342-347
Technical Paper | Reactor | doi.org/10.13182/NT71-A30982
Articles are hosted by Taylor and Francis Online.
An analytical study has been completed to define minimum critical mass parameters for a spherical region containing a 235U-H2O mixture reflected by a natural uranium-water mixture. The study indicates that for an optimum natural-H2O reflector, the calculated minimum critical mass for the central sphere lies in the range of 75 to 200 g of 235U. The analytic study was divided into three phases. In the first phase homogeneous two-region systems were examined using diffusion theory programs. The results indicated a minimum critical mass of 451-g 285U for an optimal system. In the second phase a Monte Carlo program was utilized to compute keff for uranium metal rod-H2O moderated lattices for which experimental data are available. The purpose of the second phase was to establish the validity of the Monte Carlo program as an analytical tool. In the third phase the Monte Carlo program was used to calculate 235U + H2O spheres closely reflected by an optimum lattice of natural uranium rods. The Monte Carlo program indicates that the minimum critical mass in an H2O-moderated system reflected by a uranium metal lattice is 135 ± 65 g 235U.