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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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May 2025
Latest News
Argonne’s METL gears up to test more sodium fast reactor components
Argonne National Laboratory has successfully swapped out an aging cold trap in the sodium test loop called METL (Mechanisms Engineering Test Loop), the Department of Energy announced April 23. The upgrade is the first of its kind in the United States in more than 30 years, according to the DOE, and will help test components and operations for the sodium-cooled fast reactors being developed now.
T. N. Ake, R. G. McAndrew, D. D. Whitney
Nuclear Technology | Volume 55 | Number 3 | December 1981 | Pages 583-586
Technical Paper | Fuel Cycle | doi.org/10.13182/NT81-A32802
Articles are hosted by Taylor and Francis Online.
The Babcock and Wilcox Company (B&W) normally uses part-length axial power shaping rods (APSRs) for core axial power distribution control The development and implementation by B&W and the Sacramento Municipal Utility District of a procedure for extending cycle length by removing the APSRs at the end of cycle 3 of Rancho Seco Nuclear Generating Station is explained. Increased core reactivity and hence greater cycle length were successfully achieved. Neither the reactor protection system nor normal operating limits were violated during the APSR withdrawal procedure. Further, pellet-cladding interaction was avoided, and primary coolant feedand bleed requirements were within the capacity of the plant evaporators. During the 22 h at less than full power, the average capacity factor was 81.1%, a reasonable tradeoff in light of the extension of cycle 3 by 10 effective full-power days (EFPDs). Successive use of this technique over following cycles yields average gains of 5 EFPDs per cycle.