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Division Spotlight
Human Factors, Instrumentation & Controls
Improving task performance, system reliability, system and personnel safety, efficiency, and effectiveness are the division's main objectives. Its major areas of interest include task design, procedures, training, instrument and control layout and placement, stress control, anthropometrics, psychological input, and motivation.
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.
Mohammad R. Fakory, R. T. Lahey, Jr.
Nuclear Technology | Volume 65 | Number 2 | May 1984 | Pages 250-265
Technical Paper | Nuclear Safety | doi.org/10.13182/NT84-A33410
Articles are hosted by Taylor and Francis Online.
The influence of parallel channel effects (PCE) on the effectiveness of the emergency core cooling systems in a boiling water nuclear reactor (BWR) was experimentally investigated. Specifically, the effectiveness of the core spray cooling system and the low-pressure coolant injection system during the emergency core cooling of a simulated 218-BWR/4 was studied. Experiments simulating conditions after a hypothetical design basis loss-of-coolant accident were performed in a special PCE test section in which Freon-114 was used as the working fluid. A detailed scaling analysis was performed to allow real-time simulation of the bypass leakage inflow, reflood rate, countercurrent flow limitation, core decay heat, and the size of postulated jet pump breaks. It was found that BWR core cooling could be adversely affected by postulated failure of the jet pump seals by observing the parallel channel effects.