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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.
Meeting Spotlight
Conference on Nuclear Training and Education: A Biennial International Forum (CONTE 2025)
February 3–6, 2025
Amelia Island, FL|Omni Amelia Island Resort
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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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Christmas Night
Twas the night before Christmas when all through the houseNo electrons were flowing through even my mouse.
All devices were plugged in by the chimney with careWith the hope that St. Nikola Tesla would share.
Matjaz Ravnik, Tomaz Zagar, Andreja Persic
Nuclear Technology | Volume 128 | Number 1 | October 1999 | Pages 35-45
Technical Paper | Fuel Cycle and Management | doi.org/10.13182/NT99-A3012
Articles are hosted by Taylor and Francis Online.
Calculations of fuel element burnup for realistic mixed core conditions in a 250-kW TRIGA Mark II reactor are presented. Two types of fuel elements are considered: 70% enriched FLIP and 20% enriched standard fuel elements. Two calculation models are compared. The first is based on a one-dimensional two-group diffusion approximation (the TRIGAP computer code), and the second is based on a two-dimensional four-group diffusion equation (the TRIGLAV computer code). In both cases the unit-cell group constants are generated with the WIMS code. Results of the calculations are intercompared to evaluate the influence of the two-dimensional effects on fuel element burnup. The following two-dimensional effects are considered: mixed rings, in-core water gaps, vicinity of control rods, and asymmetric core loading patterns. Relative differences in fuel element burnup of 10% on average and up to 80% in extreme cases are observed because of the two-dimensional effects. The accuracy of the calculation is estimated also by comparing the calculated results to the measurements using the reactivity method.