Abstract
Thermonuclear fusion process implementation has many material problems and one of them is related to the removal of impurities from plasma. In the International Thermonuclear Experimental Reactor (ITER), a divertor concept has been incorporated for this purpose. In this work, the development of a micromechanical model for functionally graded materials (FGMs) is presented and its application to thermal-elasto-plastic analysis is discussed for the case of the W-Cu FGMs for the ITER divertor plates. The model allows the prediction of basic properties of the FGM and computations of thermal stresses; and, in some limits, it may be used for pre-design evaluation of strain stress distributions and inelastic behavior. The model is found to be very useful at the first stages of graded materials design.
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