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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
Nuclear Energy Conference & Expo (NECX)
September 8–11, 2025
Atlanta, GA|Atlanta Marriott Marquis
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
NRC cuts fees by 50 percent for advanced reactor applicants
The Nuclear Regulatory Commission has announced it has amended regulations for the licensing, inspection, special projects, and annual fees it will charge applicants and licensees for fiscal year 2025.
Alex Pegarkov, Shawn Somers-Neal, Edgar Matida, Vinh Tang, Tarik Kaya
Nuclear Science and Engineering | Volume 196 | Number 10 | October 2022 | Pages 1161-1171
Technical Paper | doi.org/10.1080/00295639.2022.2067738
Articles are hosted by Taylor and Francis Online.
During a severe power reactor accident, the plant core can melt. The resulting mixture of molten nuclear fuel and other in-core materials is known as corium. For a Canada Deuterium Uranium (CANDU) reactor, the corium is expected to settle at the bottom of the calandria vessel, but there is a potential for some melt to flow through connecting piping and other penetrations. The flow of corium through these structures can be contained if melt solidification and thus plugging occur. A numerical model was created to simulate the flow of molten metal through an empty vertical pipe. This model was benchmarked to a previous analytical model and validated against experimental results with gallium metal (which is a metal with low melting temperature) as an alternative for corium. The numerical model predicted the penetration length of gallium with an average percent error of 10.3% when compared to the experimental penetration length results of gallium. The model was also updated to predict the corium penetration length in cooling pipes of the CANDU reactor during a severe accident.