Design calculations of a cylindrical D-T driven UO2 hybrid blanket

Recently, the subject of many scientific publications has focused on fusion-fission (hybrid) reactor systems. A few of these studies are on the experimental base and those have been confined to the neutronics of D-T drivers. Either experimental or numerical fusion neutronics have mainly concentrated on studies of purely tritium breeding blankets and the performance of fissionable materials for hybrid systems. Some experimental programs in which the main components of a hybrid blanket are kept in view have been going on. Realization of a quasiconstant power profile has been reached by using a mixed fuel and varying the fractional components of this fuel throughout the fuel zone of a hybrid blanket. Putting a neutron multiplier in front of fuel zone, this blanket has a soft neutron spectrum and this spectrum has led to an exponential power profile over longer operational periods. Without using a neutron multiplier, nearly a smooth power profile was obtained on another blanket whose structure is consistent with the earlier work by using the same mixed fuel concept. This blanket has smaller dimensions. The blanket which is subject of this study is the same as that small one with one exception of using homogeneous fissionable fuel (UO2) in the fuel zone instead of mixed one. At the same time, this study investigates a cylindrical blanket