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.
Naeem M. Abdurrahman, Georgeta Radulescu, Igor Carron
Nuclear Technology | Volume 127 | Number 3 | September 1999 | Pages 315-331
Technical Paper | Reactor Safety | doi.org/10.13182/NT99-A3004
Articles are hosted by Taylor and Francis Online.
The Saxton critical experiments, which used mixed-oxide (MOX) fuel of 6.6 wt% PuO2 in natural UO2 and UO2 fuel of 5.74 wt% 235U, are analyzed with MCNP-4B and continuous-energy cross-section libraries ENDF/B-V and ENDF/B-VI. An excellent agreement of calculated and experimental effective multiplication factors for the entire set of 1.3208-cm MOX lattices and 1.4224-cm MOX and UO2 lattices was obtained. The analysis of criticality calculations for the five different lattice pitches show a bias with lattice pitch, which led to an increase of ~0.8% when doubling the lattice pitch. Good agreement between calculated and measured data was obtained for some of the relative power distribution experiments for MOX single-region cores and MOX/UO2 multiregion cores; however, for others the agreement was less satisfactory. No significant difference in the results for relative power with the two libraries was observed.