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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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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
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.
Yasuyoshi Kato, Motomi Odamura, Hiroshi Urushihara, Hidesuke Matsushima
Nuclear Science and Engineering | Volume 133 | Number 2 | October 1999 | Pages 119-146
Technical Paper | doi.org/10.13182/NSE99-A2077
Articles are hosted by Taylor and Francis Online.
A decomposition principle has been proposed for refueling optimization in fast breeder reactors (FBRs). In refueling optimization a total multistage decision problem with nonlinear programming is decomposed into many partial problems with solvable size and linear programming by taking advantage of the FBR physics. First, the problem is decomposed into determinations of the number of refueling subassemblies in concentric annular core zones and the subassembly-by-subassembly refueling patterns. Second, the latter process is further decomposed into the determination of the refueling patterns in the equilibrium cycles and the transition cycles. Third, the simultaneous determination of the refueling patterns throughout multicycles over the plant lifetime is decomposed into a consecutive cycle-by-cycle determination. Fourth, the linear programming problems are decomposed into a sequence of smaller ones by using a decomposition algorithm for solving large-size programming.The number of fresh fuel subassemblies added at each cycle in the initial loading core through the equilibrium cycles is optimized in concentric annular refueling zones of the core. The optimization is carried out so as to maximize the average discharge burnup subject to nuclear and thermal constraints by using linear programming with an application of a revised simplex method.The refueling pattern at each cycle is determined by treating each fuel subassembly separately and by minimizing power peaking subject to the number of refueling subassemblies determined in the previous step. After optimizing the refueling patterns in the equilibrium cycles, the transition cycle patterns are determined cycle by cycle to match the equilibrium cycle patterns by means of an implicit enumeration method. An explicit formulation is worked out for the implicit enumeration method, which makes it possible to determine the refueling patterns cycle by cycle.