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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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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
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ANS designates Armour Research Foundation Reactor as Nuclear Historic Landmark
The American Nuclear Society presented the Illinois Institute of Technology with a plaque last week to officially designate the Armour Research Foundation Reactor a Nuclear Historic Landmark, following the Society’s decision to confer the status onto the reactor in September 2024.
T. Shimooke
Nuclear Technology | Volume 10 | Number 3 | March 1971 | Pages 257-272
Technical Paper | Reactor | doi.org/10.13182/NT71-A30958
Articles are hosted by Taylor and Francis Online.
Various core performances, such as power and void distributions in a core, reactivity change, and shifts of control rods, are predicted for the JPDR-1 in a three-dimensional framework by means of the one-energy-group coarse-mesh approximation of the boiling water reactor (BWR) core. The predictions are checked in detail with experimental data that were accumulated by “the core-performance assessment experiments” done throughout the life of the JPDR-1 core. The data include y-probing data of the core at the exposure of each 1000 MWd/ton (approximately) core outlet void fractions measured directly by voidmeters, logbook records of the control rod patterns, heat-balance data for the precise core outputs, and others. In conclusion, the one-energy-group coarse-mesh approximation of the BWR is proved to be satisfactory for describing the global core performances of the JPDR-1 for burnup cases. The global power distributions can be calculated, e.g., with 4% standard deviation in the channel power sharing, and this is accurate enough to predict the core reactivity within 0.3% Δk/k error at 6000-MWd/ton exposure. The observed discrepancy, 0.9% Δk/k in the core reactivity at 6000-MWd/ton exposure (i.e., 10 to 15% error of the burnup change of reactivity), is discussed, with the final suggestion that the local power and exposure distribution in a core should be studied first, among others, for better achievement of the global core description.