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
Operations & Power
Members focus on the dissemination of knowledge and information in the area of power reactors with particular application to the production of electric power and process heat. The division sponsors meetings on the coverage of applied nuclear science and engineering as related to power plants, non-power reactors, and other nuclear facilities. It encourages and assists with the dissemination of knowledge pertinent to the safe and efficient operation of nuclear facilities through professional staff development, information exchange, and supporting the generation of viable solutions to current issues.
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.
W. L. Pearl, E. G. Brush, G. G. Gaul, G. P. Wozadlo
Nuclear Technology | Volume 1 | Number 3 | June 1965 | Pages 235-245
Technical Paper | doi.org/10.13182/NT65-A20508
Articles are hosted by Taylor and Francis Online.
Incoloy-800® fuel-cladding material has been corrosion-tested under heat-transfer conditions at metal temperatures up to 1410° F (766° C) in specially designed out-of-pile superheat facilities. The hydrogen and oxygen contents of the steam were controlled to simulate those found in boiling-water-reactor systems. The corrosion data from the 4000-h heat-transfer tests indicated good corrosion resistance up to at least 1300° F (704° C) metal temperature. A compositionally changed layer developed at the metal-oxide interface. The changed layer depth appeared to be a function of time and temperature of exposure. The descaled weight-loss data for the sheaths operated at a metal temperature of 1100 to 1300° F (593 to 704° C) indicate that greater than 80% of the oxide corrosion product adhered during the first 1000-h exposure, but only about 50% of the total oxidation product remained after 4000 h. The uniform corrosion experienced by the Incoloy-800® when exposed isothermally to 1050 and 1150° F (566 and 621° C) for 10 000h indicates an initially high-corrosion rate that decreases to a lower constant rate within the first 1000 h. An insignificant amount of the oxide was lost to the system.