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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
International Conference on Mathematics and Computational Methods Applied to Nuclear Science and Engineering (M&C 2025)
April 27–30, 2025
Denver, CO|The Westin Denver Downtown
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
DTE Energy studying uprate at Fermi-2, considers Fermi-3’s prospects
DTE Energy, the owner of Fermi nuclear power plant in Michigan, is considering an extended uprate for Unit 2 that would increase its 1,100-MW generation capacity by 150 MW.
R. W. Bowring, C. L. Spigt
Nuclear Science and Engineering | Volume 22 | Number 1 | May 1965 | Pages 1-13
Technical Paper | doi.org/10.13182/NSE65-A19756
Articles are hosted by Taylor and Francis Online.
Stability and burnout natural-circulation tests on an electrically heated 7-rod cluster were carried out to obtain data relevant to the Halden II reactor. The object of the tests was to measure the maximum channel powers obtainable without burnout at pressures up to 28 atm and various inlet subcoolings. The test-section heat flux was essentially uniform, but local heat-flux peaks were introduced at hot patches to probe burnout. It was found that at 28 atm and up to 6°C inlet subcooling, a channel power of nearly 600 kW could be reached without burnout or instability; increasing the subcooling further, reduced the burnout power. The instability channel power threshold was investigated and found to decrease with decreasing pressure. In addition, the natural-circulation inlet velocity was measured at various constant pressures and values of inlet-subcooler heat removal, as a function of channel power up to and in the hydraulic instability region. Flow oscillations of about 1-sec period were observed and recorded together with the burnout detector signal at trip under these conditions.