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- W1247103699 abstract "This paper reports on an in-core nuclear fuel management code for pressurized water reactor reload design developed that combines the stochastic optimization technique of simulated annealing with a computationally efficient core physics model based on second-order accurate generalized perturbation theory. The approach identifies the placements of feed fuel, exposed fuel with assembly orientations, and burnable poisons within the core lattice that optimize fuel cycle performance or thermal margin according to one of the following objectives: maximization of k{sub eff} at a target end-of-cycle (EOC) burnup, minimization of the maximization radial power peaking over the cycle, or maximization of region average discharge burnup, and subject to constraints on radial power peaking, discharge burnup and moderator temperature coefficient." @default.
- W1247103699 created "2016-06-24" @default.
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- W1247103699 date "1991-07-01" @default.
- W1247103699 modified "2023-09-27" @default.
- W1247103699 title "In-core nuclear fuel management optimization for pressurized water" @default.
- W1247103699 hasPublicationYear "1991" @default.
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