Comparative study of radioactivity and afterheat in several fusion reactor blanket designs

The induced radioactivity and afterheat in five recently presented fusion reactor blanket designs were calculated. These designs differ in the choices of structural material, coolant, and neutron multiplier. Nevertheless, the radioactivity levels at shutdown after a 2-yr operation are within a factor of 4 of each other and are clustered at approximately 1 Ci/W(th). However, the long-term radioactivity (greater than 200 yr) is greatest for niobium structures and least for aluminun. For niobium, the level of long-term activity is approximately 5 x 10-5 Ci/W(th), whereas for aluminum, the level drops to approximately10-7 Ci/W(th) just several weeks after shutdown. This last result will be modified by the inclusion of trace elements and impurities. Afterheat levels are found to vary from 1/2 to 5 percent of the thermal operating power, depending on design and the choice of structural material. Importantly, however, the afterheat power density is only approximately 0.2 W/ cm3 at most and this is roughly a factor of 10 to 60 less than the afterheat power density in fast breeder reactors. Biological hazard potential (BHP) values are calculated for all designs by the pessimistic approach of dividing the activity in Ci/kW(th) by the lowest maximum permissible concentration value, in Ci/km3 of air, given in U. S. Atomic Energy Commission rules, Title 10, Part 20. In all cases, the BHP nevertheless drops below 1 km3/kW(th) 20 yr after shutdown following a 2-yr operation. The key isotopes contributing to radioactivity, afterheat, and BHP are listed for future reference. (U.S.)