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
Nuclear Installations Safety
Devoted specifically to the safety of nuclear installations and the health and safety of the public, this division seeks a better understanding of the role of safety in the design, construction and operation of nuclear installation facilities. The division also promotes engineering and scientific technology advancement associated with the safety of such facilities.
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.
R. D. Waddell, Jr.
Nuclear Technology | Volume 11 | Number 4 | August 1971 | Pages 491-501
Technical Paper | Symposium on Fuel Rod Failure and Its Effect / Fuel | doi.org/10.13182/NT71-A30846
Articles are hosted by Taylor and Francis Online.
The Zircaloy-clad fuel rods of a light-water reactor will deform by swelling during the thermal transient associated with a loss-of-coolant accident (LOCA). This swelling may cause coolant channel blockage of such magnitude that emergency cooling may be impaired. To investigate the effect of tube swelling on coolant flow area, a series of multirod transient burst tests have been conducted under various conditions of internal pressure and heating rates. Results to date have shown a wide range of coolant channel blockage for internal pressures up to 400 psig.
