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
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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Nuclear Science and Engineering
May 2025
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.
J. Rest
Nuclear Technology | Volume 56 | Number 3 | March 1982 | Pages 553-564
Technical Paper | Nuclear Fuel | doi.org/10.13182/NT82-A32914
Articles are hosted by Taylor and Francis Online.
The interrelationship between fuel fracturing (microcracking), temperature scenario, and fission-gas-bubble response is investigated. The fission-gas-bubble behavior is described using the FASTGRASS computer code. A model, based on the work of DiMelfi and Deitrich describing ductile/brittle fuel behavior, has been incorporated into the FASTGRASS analysis. The predictions of fission-gas release, radial distribution of released gas, radial distribution of microcracking, and fuel temperatures are compared with the results of transient direct-electrical-heating experiments on irradiated light water reactor fuel. Finally, results of analyses for Three Mile Island Unit 2 type accident conditions are presented and implications for microcracking and fission-gas behavior during this accident are discussed.
