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Division Spotlight
Nuclear Criticality Safety
NCSD provides communication among nuclear criticality safety professionals through the development of standards, the evolution of training methods and materials, the presentation of technical data and procedures, and the creation of specialty publications. In these ways, the division furthers the exchange of technical information on nuclear criticality safety with the ultimate goal of promoting the safe handling of fissionable materials outside reactors.
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.
Bernhard Kienzler, Rainer H. Köster
Nuclear Technology | Volume 71 | Number 3 | December 1985 | Pages 590-596
Technical Paper | Radioactive Waste Management | doi.org/10.13182/NT85-A33681
Articles are hosted by Taylor and Francis Online.
Evaluation of the long-term radionuclide release from cemented waste forms in contact with solutions like salt brine requires a detailed chemical analysis of the corrosion processes. The results can be integrated into a theoretical model. For this purpose, experiments were performed with simulated cemented radioactive waste forms, giving the concentration profiles of the elements involved in the corrosion process. The profiles are measured parallel to the direction of corrosion, mainly by electron microprobe analysis. The profiles are compared with profiles computed with the recently developed DIFMOD computer code. It computes both leaching of specimen transportation of the reactive ions, such as Mg2+ and contained in a quinary brine, into the cement product and the chemical reactions occurring in the waste form. On the basis of diffusion constants from the literature and fitted material constants, a good agreement between the calculated and measured concentration profiles has been achieved. The penetration of the corrosion front into waste forms is computed as an example of a practical application of the model.