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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.
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Conference on Nuclear Training and Education: A Biennial International Forum (CONTE 2025)
February 3–6, 2025
Amelia Island, FL|Omni Amelia Island Resort
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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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2024: The Year in Nuclear—July through September
Another calendar year has passed. Before heading too far into 2025, let’s look back at what happened in 2024 in the nuclear community. In today's post, compiled from Nuclear News and Nuclear Newswire are what we feel are the top nuclear news stories from July through September 2024.
Stay tuned for the top stories from the rest of the past year.
Yasushi Nomura, James L. Anderson
Nuclear Technology | Volume 87 | Number 4 | December 1989 | Pages 912-925
Technical Paper | TMI-2: Decontamination and Waste Management / Nuclear Safety | doi.org/10.13182/NT89-A27685
Articles are hosted by Taylor and Francis Online.
The refill phenomena occurring from 200 to 217 min of the Three Mile Island Unit 2 accident were analyzed by using measurement data including the reactor coolant system (RCS) pressure and the pressurizer level. At 200 min, the high-pressure injection (HPI) system began to inject water into the RCS, resulting in a primary system depressurization due to steam condensation; and the pressurizer water drained into the reactor vessel, increasing the liquid level at the core. It is believed that the core was completely covered by water by ∼207 min, when the pressurizer level decrease and the RCS depressurization stopped. Continued HPI resulted in increasing hot-leg water levels; and the pressurizer level began to increase at ∼210 min, when water reached the level of the surgeline entrance to the hot leg. Analysis of the refill assuming uniform liquid levels in the RCS fails to predict the observed phenomena. A set of equations describing the refill phenomena and accounting for compression of noncondensable gases has been derived from theoretical considerations, and solutions for water levels throughout the RCS have been obtained to correctly predict the phenomena occurring during the refill period.