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!
Latest Magazine Issues
Apr 2025
Jan 2025
Latest Journal Issues
Nuclear Science and Engineering
May 2025
Nuclear Technology
Fusion Science and Technology
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.
Melville A. Feraday, Moon T. Foo, Ross D. Davidson, John E. Winegar
Nuclear Technology | Volume 58 | Number 2 | August 1982 | Pages 233-241
Technical Paper | Nuclear Fuel | doi.org/10.13182/NT82-A32934
Articles are hosted by Taylor and Francis Online.
The stability of Al-USiAl dispersion fuels and Al-U alloys was examined at temperatures between 200 and 400°C for times up to 93 days. The Al-U alloys, which contained 21 to 37 wt% uranium, did not show any dimensional or metallurgical changes after 93 days at 400°C. After being heated at 200°C, the Al-USiAl fuel showed no dimensional or metallurgical changes. However, between 250 and 400°C, the USiAl particles reacted with the aluminum matrix to form UAl3 and UAl4. The amount of reaction increased with temperature and time. The aluminum diffuses into the USiAl particles along grain boundaries to form the new Al-U compounds. Although the Al-USiAl fuel showed thermal instability at 250°C and above, the in-reactor behavior under normal operation is expected to be satisfactory since fuel temperatures will generally be <200°C.