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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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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.
J. L. Kaae, S. A. Sterling, L. Yang
Nuclear Technology | Volume 35 | Number 2 | September 1977 | Pages 536-547
Advanced and Improved Fuel and Application | Coated Particle Fuel / Fuel | doi.org/10.13182/NT77-A31914
Articles are hosted by Taylor and Francis Online.
Two-phase mixtures of pyrolytic carbon (PyC) and either silicon carbide or zirconium carbide are commonly called alloyed carbons and can be deposited on nuclear fuel particles by a combination of the well-known techniques of depositing carbon and the carbides. The silicon-alloyed carbons have properties that offer substantial improvements in coated-particle performance, while the zirconium-alloyed carbons that have been investigated have been found to be lacking in two of the properties essential for improved coating performance. The properties of the silicon-alloyed carbons that give rise to the improvements in performance are higher strength, smaller irradiation-induced dimensional changes, and a lower diffusivity for cesium than pure PyC’s. These properties have significant implication to coated-particle design. Also, the silicon-alloyed carbons do not offer fundamental difficulties to the head-end of fuel reprocessing.