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
Reactor Physics
The division's objectives are to promote the advancement of knowledge and understanding of the fundamental physical phenomena characterizing nuclear reactors and other nuclear systems. The division encourages research and disseminates information through meetings and publications. Areas of technical interest include nuclear data, particle interactions and transport, reactor and nuclear systems analysis, methods, design, validation and operating experience and standards. The Wigner Award heads the awards program.
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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Nuclear Technology
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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.
Jack L. Collins, Morris F. Osborne, R. A. Lorenz
Nuclear Technology | Volume 77 | Number 1 | April 1987 | Pages 18-31
Technical Paper | Fission Reactor | doi.org/10.13182/NT87-A33948
Articles are hosted by Taylor and Francis Online.
Fission product release tests and control tests recently conducted at Oak Ridge National Laboratory have provided new experimental data that help characterize the mechanism of fission product tellurium release behavior under severe light water reactor accident conditions. Release of tellurium from the fuel rod segments has been found to be dependent on the rate and extent of cladding oxidation. Tellurium was observed to be significantly retained by metallic Zircaloy cladding at test temperatures up to 2000°C. The results indicate that the tellurium was bound by the Zircaloy cladding as zirconium telluride, but once the available metallic zirconium was oxidized by the steam, tellurium was released in favor of continued zirconium oxide formation. The collection behavior of the released tellurium indicated that it was probably released from the fuel rods as tellurides of tin, cesium, and rubidium rather than as elemental tellurium.
