Activation of beryllium in a fusion power plant

Abstract The activation and transmutation behaviour of beryllium in the first wall of a fusion power plant has been studied using the up-to-date inventory code FISPACT-97. Assuming detritiation, the activity and dose rate will be determined by the impurities initially present in the material. The possible influences of sequential charged particle reactions and of trace amounts of Th and U as fissionable actinides are examined but found unlikely to be important. Beryllium appears to offer the prospect of reuse in further plant following minimal processing after decay storage for about 50 yr.