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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.
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2024 ANS Winter Conference and Expo
November 17–21, 2024
Orlando, FL|Renaissance Orlando at SeaWorld
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
The short life of the Hallam plant
The Hallam nuclear power plant in Nebraska, about 25 miles southwest of Lincoln, was a 75-MWe sodium-cooled, graphite-moderated reactor operated by Consumers Public Power District of Nebraska (CPPD). It was co-located with the Sheldon Power Station, a conventional coal-fired plant. The facility had a shared control room and featured a shared turbo generator that could accept steam from either heat source.
Masahiro Furuya, Takanori Fukahori, Shinya Mizokami
Nuclear Technology | Volume 158 | Number 2 | May 2007 | Pages 191-207
Technical Paper | Nuclear Reactor Thermal Hydraulics | doi.org/10.13182/NT07-A3835
Articles are hosted by Taylor and Francis Online.
To investigate the stability of a boiling water reactor (BWR), the SIRIUS-F facility was designed and built for highly accurate simulation of thermal-hydraulic (channel) instabilities and coupled thermal hydraulics-neutronics instabilities of the BWR. By using two sets of measured void-fraction distributions in a reactor core section of the SIRIUS-F facility, a real-time void-reactivity feedback simulation was performed on the basis of the modal point kinetics of reactor neutronics and fuel rod thermal conduction. A noise analysis method was performed to calculate decay ratios and resonance frequencies from dominant poles of transfer function based on the AR method using time-series measurement data of a core inlet flow of the facility.Channel and regional stability experiments were conducted for a wide range of operating conditions, including maximum power points along the minimum pump speed line and the natural circulation line of advanced BWR plants. The experimentally obtained decay ratios and resonance frequencies are in good agreement with those calculated by the linear stability analysis code ODYSY. The SIRIUS-F experimental results demonstrated stability characteristics as a function of power and revealed a sufficiently large stability margin even under hypothetical power level conditions.