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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.
Seihiro Itoya, F. D. Shum, Jun-Ichiro Otonari, Hideo Nagasaka
Nuclear Technology | Volume 80 | Number 3 | March 1988 | Pages 349-359
Technical Paper | Fission Reactor | doi.org/10.13182/NT88-A34059
Articles are hosted by Taylor and Francis Online.
The advanced boiling water reactor (ABWR) is designed to represent the next generation of boiling water reactors (BWRs), to be introduced into commercial operation in the 1990s. The response of the ABWR to loss-of-coolant accidents (LOCAs) was simulated in the full integral simulation test (FIST)-ABWR test facility. However, the emergency core cooling system structure was somewhat different from the current ABWR design. The LOCA experimental results of FIST-ABWR showed that a core was completely covered by a two-phase mixture and cooled by natural circulation without any rod heatup. The SAFER03 computer code has a newly developed evaluation model for the analysis of BWR LOCAs. SAFER03 analyses with the FIST-ABWR test data were performed to assess its ability to predict thermal-hydraulic responses for various postulated break locations in an ABWR. The analytical results indicate that SAFER03 accurately predicted pressure history, down-comer level response, and key phenomena, such as no core uncovery and no rod heatup. Consequently, it was confirmed that SAFER03 is applicable for ABWR LOCA analyses.