Parameter survey of transuranium incineration in fusion reactor blanket

In this study, transuranium (TRU) elements were loaded in the blanket of a fusion reactor and incinerated through fission reaction or nuclear transmutation, utilizing abundant neutron in a fusion reactor. To study the process, it is necessary to perform burn-up calculation of TRU. We used ORIGEN-2 code for the burn-up calculation. First we compared TRU incineration in the fast neutron blanket with that in the thermal neutron blanket with the same first wall loading. Then we considered several kinds of conditions for the incineration as follows; (1) graphite density in thermal neutron blanket, (2) irradiation time both in fast and thermal neutron blanket, (3) burn-up of spent fuel, (4) fuel recovery level, and (5) FBR spent fuel instead of PWR fuel. To evaluate above mentioned conditions, we compared the hazard indices calculated under these conditions. The result showed that fast neutron blanket is more effective for TRU incineration than thermal neutron blanket. (author)