摘要: Neutronic and heat transfer calculations have been performed for two helium cooled blankets for the INTOR design. The neutronic calculations show that the local tritium breeding ratios, both for the ceramic blanket (Li sub 2 SiO s... 展开 Neutronic and heat transfer calculations have been performed for two helium cooled blankets for the INTOR design. The neutronic calculations show that the local tritium breeding ratios, both for the ceramic blanket (Li sub 2 SiO sub 3 ) and for the liquid blanket (Li sub 17 Pb sub 83 ) solutions, are 1.34 for natural tritium and about 1.45 using 30% Li exp 6 enrichment. The heat transfer calculations show that it is possible to cool the divertor section of the torus (heat flux = 1.7 MW/m exp 2 ) with helium with an inlet pressure of 52 bar and an inlet temperature of 40 exp 0 C. The temperature of the back face of the divertor can be kept at 130 exp 0 C. With helium with the same inlet conditions it is possible to cool the first wall as well (heat flux = 0.136 MW/m exp 2 ) and keep the back-face of this wall at a temperature of 120 exp 0 C. For the ceramic blanket we use helium with 52 bar inlet pressure and 400 exp 0 C inlet temperature to ensure sufficiently high temperatures in the breeder material. The maximum temperature in the pressure tubes containing the blanket is 450 exp 0 C, while the maximum breeder particle temperature is 476 exp 0 C. (ERA citation 09:030008) 收起