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The Monte Carlo (MC) code MCNP is the reference tool in fusion neutronics, allowing the description and analysis of full and detailed 3-D geometry of a tokamak machine. The geometrical models of the components used are typically available through computer aided design (CAD) files: the main benefits of this system are related to its portability and compatibility with several tools commonly used in...
This paper develops a METRIC-like model to optimize inventory allocation of repairable spares in a three-echelon supply system. Supply availability is selected as the optimizing object of the model, and the total ordering cost of repairable spares is taken as the constraint condition. The optimal allocation of repairable spares is reached by the marginal analysis algorithm. Then the established model...
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