ANS is committed to advancing, fostering, and promoting the development and application of nuclear sciences and technologies to benefit society.
Explore the many uses for nuclear science and its impact on energy, the environment, healthcare, food, and more.
Division Spotlight
Isotopes & Radiation
Members are devoted to applying nuclear science and engineering technologies involving isotopes, radiation applications, and associated equipment in scientific research, development, and industrial processes. Their interests lie primarily in education, industrial uses, biology, medicine, and health physics. Division committees include Analytical Applications of Isotopes and Radiation, Biology and Medicine, Radiation Applications, Radiation Sources and Detection, and Thermal Power Sources.
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.
Masaaki Mori and Mitsuru Kawamura, Koichi Yamate
Nuclear Science and Engineering | Volume 121 | Number 1 | September 1995 | Pages 41-51
Technical Paper | doi.org/10.13182/NSE95-A24127
Articles are hosted by Taylor and Francis Online.
A benchmark study is presented of new methodologies of the Studsvik CASMO-4/SIMULATE-3 advanced nuclear design code system against a pressurized water reactor (PWR)-type mixed-oxide (MOX) fuel critical experiment with high plutonium content. Both CASMO-4 two-dimensional transport core calculations and SIMULATE-3 nodal core calculations that use the pin power reconstruction model are performed for the experimental geometries. All the assembly two-group constants for SIMULATE-3, including those for MOX assemblies, are generated by CASMO-4 singleassembly calculations. The CASMO-4 improved transmission probability method and the SIMULATE-3 improved nodal and spectral interaction models are verified to be effective for accurate prediction of the pin power distribution inside high plutonium content PWR MOX assemblies and UO2 assemblies that are adjacent to the MOX assemblies.
