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Division Spotlight
Robotics & Remote Systems
The Mission of the Robotics and Remote Systems Division is to promote the development and application of immersive simulation, robotics, and remote systems for hazardous environments for the purpose of reducing hazardous exposure to individuals, reducing environmental hazards and reducing the cost of performing work.
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.
Tien-Ko Wang, Liang-Chen Shiao, Chia-Lian Tseng
Nuclear Technology | Volume 91 | Number 3 | September 1990 | Pages 413-418
Technical Paper | Technique | doi.org/10.13182/NT90-A34462
Articles are hosted by Taylor and Francis Online.
A method is developed to estimate spent-fuel burnup using gamma-ray spectrometry of the short-lived fission product 140La. The 140La activity was established by reirradiating the spent fuel in a reactor core. Based on the measured 140La activity, burnup values can be deduced by iterative calculations. In this method, the fuel irradiation history is not needed. To verify its validity, burnup values deduced from 140La activities were compared with those deduced from the conventional long-lived I37Cs activities and 134Cs/137Cs activity ratios; good agreement was obtained. This method is applicable to reactors loaded with highly enriched, thin plate-type fuels.