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Division Spotlight
Nuclear Installations Safety
Devoted specifically to the safety of nuclear installations and the health and safety of the public, this division seeks a better understanding of the role of safety in the design, construction and operation of nuclear installation facilities. The division also promotes engineering and scientific technology advancement associated with the safety of such facilities.
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.
Adly B. Wahba, Fritz Steinhoff
Nuclear Technology | Volume 87 | Number 4 | December 1989 | Pages 1086-1096
Late Paper | TMI-2: Decontamination and Waste Management / Heat Transfer and Fluid Flow | doi.org/10.13182/NT89-A27699
Articles are hosted by Taylor and Francis Online.
The thermal-hydraulic code A THLET used to analyze the Three Mile Island Unit 2 accident was developed at the Gesellschaft für Reaktorsicherheit in the Federal Republic of Germany for safety analysis of pressurized water reactors with U-tube steam generators. First calculations of phase 1 of the accident without simulating the secondary sides were preliminary and have shown the need for accurate heat flow rates in the steam generators. The available values resulted in an incorrect system pressure behavior. Second calculations with detailed simulation of the once-through steam generator provided interesting information like the influence of flow resistance in the aspirator on cold-leg temperature and the dependence of system behavior on the rate and position of auxiliary feedwater injection.