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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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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.
Michael W. J. Lewis, Charles S. Campbell
Nuclear Technology | Volume 55 | Number 2 | November 1981 | Pages 460-469
Technical Paper | Materials | doi.org/10.13182/NT55-460
Articles are hosted by Taylor and Francis Online.
Steam generators for liquid-metal fast breeder reactors may be subject both to fretting wear as a result of flow-induced vibrations and to wear from larger amplitude sliding movements caused by thermal changes. Wear under these conditions is strongly adhesive so that in tests simulating the larger amplitude sliding of tubing through support plates, mechanical interaction of the wear scars results in high pseudo-friction forces for ferritic steels at the extremities of movement. With austenitic steel combinations in such tests, less wear is found but at temperatures above 500°C static adhesion after a period of dwell can give increased axial forces to initiate sliding, for example, up to three times the contact force at 560°C. A number of test mechanisms have been developed to evaluate the impact, impact-slide, and rubbing fretting behavior of these materials in sodium. With hemisphere-on-flat geometry, specific wear rates for austenitic steel combinations in impact-slide increase with temperature and decrease with time, while specific wear rates for ferritic steel combinations are approximately an order of magnitude greater (10−14 to 10−13 m3/Nm). In rubbing fretting, wear rates are broadly similar for austenitic and ferritic steel combinations. Specific wear rates decrease with slip amplitude and are of the order of 3 × 10−16 m3/Nm at 10 µm and 3 × 10−15 m3/Nm in excess of 100 µm.