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
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.
A. B. Reynolds, C. A. Erdman, M. Kirbiyik
Nuclear Technology | Volume 26 | Number 2 | June 1975 | Pages 165-171
Technical Paper | Reactor Siting | doi.org/10.13182/NT75-A24415
Articles are hosted by Taylor and Francis Online.
Methods to calculate bounding values for the generation of fuel vapor during disassembly and during expansion of the fuel after disassembly in a fast-reactor core-disruptive accident were developed. Isentropic expansion of the fuel following disassembly with no fuel mixing before expansion was assumed. It was necessary to develop consistent thermodynamic fuel properties for the analysis. The method was applied to a liquid-metal fast breeder reactor disassembly, first with sodium in the core and then with sodium removed. Bounding values were also compared to lower values obtained by assuming mixing and thermal equilibrium of the fuel prior to expansion. For the bounding calculation with sodium removed, 4.6% of the fuel vaporized when the expanded fuel occupied all of the available volume. This value was reduced to 0.9% when mixing and thermal equilibrium prior to expansion was assumed.