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Division Spotlight
Radiation Protection & Shielding
The Radiation Protection and Shielding Division is developing and promoting radiation protection and shielding aspects of nuclear science and technology — including interaction of nuclear radiation with materials and biological systems, instruments and techniques for the measurement of nuclear radiation fields, and radiation shield design and evaluation.
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.
R. A. Bradley, B. A. Thiele
Nuclear Technology | Volume 35 | Number 2 | September 1977 | Pages 353-358
Performance and Performance Modeling | Coated Particle Fuel / Fuel | doi.org/10.13182/NT77-A31895
Articles are hosted by Taylor and Francis Online.
Fuel for the high-temperature gas-cooled reactor is in the form of microspheres surrounded by high-density impermeable coatings to retain fission products. Recent irradiation tests indicated that the high-density carbon layer of Biso coatings may become permeable to krypton, xenon, and CO during irradiation. In-reactor gas release measurements showed the particles were impermeable to fission gases at the beginning of the testy but released significant quantities of krypton and xenon after a period of irradiation. Although postirradiation examination by visual, ceramographic, and radiographic techniques indicated that all particles were intact, gas content measurement showed that particles receiving a significant fast fluence contained only a small fraction of the expected krypton and xenon, while those receiving low fluence retained almost all the fission gas. The results of these experiments indicate that the permeability of the coatings is due to fast-neutron-induced structural changes in the pyrocarbon.