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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
Conference on Nuclear Training and Education: A Biennial International Forum (CONTE 2025)
February 3–6, 2025
Amelia Island, FL|Omni Amelia Island Resort
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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Christmas Night
Twas the night before Christmas when all through the houseNo electrons were flowing through even my mouse.
All devices were plugged in by the chimney with careWith the hope that St. Nikola Tesla would share.
Hiroaki Suzuki, Masanori Naitoh, Atsuo Takahashi, Marco Pellegrini, Hidetoshi Okada
Nuclear Technology | Volume 186 | Number 2 | May 2014 | Pages 255-262
Technical Paper | Reactor Safety | doi.org/10.13182/NT13-42
Articles are hosted by Taylor and Francis Online.
The Great East Japan Earthquake and tsunami on March 11, 2011, mark the start of the nuclear accident at the Fukushima Daiichi nuclear power plant. Progression of the accident has been analyzed with the SAMPSON code. SAMPSON was originally designed as a large-scale simulation system with the maximum use of mechanistic models and theoretically based equations. In the progression analysis done for Unit 2, SAMPSON could reproduce the pressure transient of the reactor pressure vessel (RPV) reasonably well by assuming partial load operation of the reactor core isolation cooling system (RCIC). The pressure transient of the primary containment vessel was reproduced reasonably well by assuming torus room flooding. After the RCIC trip and manual opening of the steam relief valve, SAMPSON predicted the damage to the upper part of the fuel assemblies near the core center and RPV failure due to creep rupture. More than 91 wt% of the core debris relocated to the lower plenum was as particles, and the major constituents were UO2, Zr, and ZrO2 by SAMPSON analysis.