Activation analysis of the PULSAR-I fusion power reactor

PULSAR-I is a 1000 MWe pulsed inductively-driven tokamak design. The reactor uses a helium-cooled SiC composite as a structural material and Li/sub 2/O as a breeder. At shutdown, the blanket and shield activities are 693 and 77.9 MCi, respectively. The blanket activity drops by more than two orders of magnitude during the first hour following its replacement. The shield activity drops more slowly than the blanket's. One year after shutdown, the shield activity drops to the same level as the blanket activity. The decay heat generated in the blanket drops from 17.3 MW at shutdown to only 1.14/spl times/10/sup -3/ MW within a week following shutdown. The total of 1.135 MW of decay heat is generated in the shield at shutdown. The shield's decay heat drops by three orders of magnitude during the first day after shutdown. The biological hazard potentials produced in the blanket and shield at shutdown are 33.8/spl times/10/sup 9/ and 4.3/spl times/10/sup 9/ m/sup 3/ air, respectively. The radwaste classification of the reactor structure is evaluated according to both the NRC 10CFR61 and Fetter waste disposal concentration limits. If the first wall and blanket are disposed of together, the waste package will qualify for Class C Low Level Waste (LLW) disposal. After 30 years of operation, the shield will qualify for disposal as Class A LLW. Assuming a 25 /spl mu/Sv/h limit for hands-on maintenance, only remote maintenance will be allowed at any location inside the containment.