STRESS ANALYSIS OF THE TOKAMAK ENGINEERING TEST BREEDER BLANKET

This report presents the design features of the hybrid reactor blanket and main parameters of it. The stress analysis performed using computer codes SAP5p and SAP6 with the three kinds of blanket module loadings, i. e, the pressure of coolant,the blanket weight ant the thermal loading. Numerical calculation results indicate that the stresses of the blanket are smaller than the allowable ones of the material, the blanket design is therefore reasonable.