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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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Nuclear Technology
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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.
Pin-Wu Kao, Jing-Tong Yang, Chian-Yeh Ho, Cheng-Hsien Chou, Ruey-Chang Huang, and, Ta-Chieh Sun
Nuclear Technology | Volume 99 | Number 2 | August 1992 | Pages 222-234
Technical Paper | Nuclear Fuel Cycle | doi.org/10.13182/NT92-A34692
Articles are hosted by Taylor and Francis Online.
Power reactor benchmark calculations using the advanced code package CASMO-3 /SIMULATE-3 with new models have been performed for nine cycles of Chinshan Unit 1 and six cycles of Kuosheng Unit 1. The fuel reload designs include gadolinia as a burnable absorber, natural uranium axial blankets, and fuel from different vendors. The calculated results for cold critical tests and traversing in-core probe (TIP) responses are compared with measured data. These comparisons show that the new modeling accurately predicts important physics parameters for power reactors, and it is more accurate than the conventional model. However, more studies of the TIP adaption model are needed in order to gain more experience for its application.