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Division Spotlight
Accelerator Applications
The division was organized to promote the advancement of knowledge of the use of particle accelerator technologies for nuclear and other applications. It focuses on production of neutrons and other particles, utilization of these particles for scientific or industrial purposes, such as the production or destruction of radionuclides significant to energy, medicine, defense or other endeavors, as well as imaging and diagnostics.
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.
Robert E. Rothe, C. L. Schuske, E. E. Hicks
Nuclear Technology | Volume 7 | Number 6 | December 1969 | Pages 505-512
Reactor | doi.org/10.13182/NT69-A28369
Articles are hosted by Taylor and Francis Online.
Experimental data are presented to show the conditions under which a complex fissile system may be conservatively approximated by a simpler system. The complex system consists of an unpoisoned uranium-solution slab in contact, on one face, with a thick region of heavily boronpoisoned uranium solution. The simpler system consists of an unpoisoned uranium-solution slab reflected, on one face, by Plexiglas. A calculated correction to yield a similar result for water is also presented. Use of this approximation will simplify a nuclear-safety engineer's evaluation of complex interacting fissile regions containing heavily poisoned and unpoisoned vessels. Measured critical thicknesses are reported for uranium-solution slabs unreflected, reflected on one face only, and reflected on both faces by Plexiglas. These data and calculations on infinitesolution slabs similarly reflected confirm that the critical height decreases linearly as the percent of the surface area reflected increases.