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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!
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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. P. Schuman
Nuclear Technology | Volume 56 | Number 2 | February 1982 | Pages 254-264
Technical Paper | Radioactive Waste Management | doi.org/10.13182/NT82-A32852
Articles are hosted by Taylor and Francis Online.
A number of pellets and highly durable glasses, prepared from nonradioactive simulated high-level waste calcines, have been leach tested. The leach tests were patterned on the International Atomic Energy Agency standard test and the proposed Materials Characterization Center tests. Most tests were made with static distilled water at 25, 70, 95, 250, and 350°C and in refluxing distilled water at 95°C. Leach rates were determined by analyzing the leachate by instrumental activation analysis or spectrochemical analysis and from weight loss. The leach tests were run on solid pieces of glass (cast and core-drilled cylinders and broken pieces) and on coarse ground glass. Solid pieces gave higher leach rates than ground glass. Cesium, molybdenum, sodium, and weight loss leach rates of solid pieces of glass in distilled water were comparable and varied from <10-7 g/cm2 day at 25°C to ∼10-1 g/cm2 day at 250°C. The leach rates in static distilled water at 95°C were lower than those in refluxing distilled water at the same temperature. Even at 25°C, sodium, cesium, and molybdenum readily leached from the porous pellets, but the pellets showed no visible attack, even at 250°C.