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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
ANS Student Conference 2025
April 3–5, 2025
Albuquerque, NM|The University of New Mexico
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
X-energy, Dow apply to build an advanced reactor project in Texas
Dow and X-energy announced today that they have submitted a construction permit application to the Nuclear Regulatory Commission for a proposed advanced nuclear project in Seadrift, Texas. The project could begin construction later this decade, but only if Dow confirms “the ability to deliver the project while achieving its financial return targets.”
H. Austregesilo, T. Hollands (GRS)
Proceedings | 2018 International Congress on Advances in Nuclear Power Plants (ICAPP 2018) | Charlotte, NC, April 8-11, 2018 | Pages 746-754
The thermal-hydraulic system code ATHLET is one main component of the German code package AC2, developed at GRS for comprehensive analyses of nuclear power plants under design basis and beyond design basis accident conditions. In the frame of code validation, five of the eight experiments performed in the German integral test facility PKL within the OECD/NEA joint project PKL-3 have been selected for the evaluation of code capabilities. One main focus has been the simulation of station blackout (SBO) scenarios. Calculation results show that ATHLET can adequately reproduce the main experimental phenomena, including pressure and temperature evolutions, coolant distribution in the primary circuit, and restart of natural circulation in the loop with emergency feedwater injection. Another main contribution to code validation was the simulation of small break loss-of-coolant (SBLOCA) tests. These tests have been designed as counterpart tests to experiments previously performed at the Japanese LSTF facility, providing a sound indication of the scalability of code results.