Environmental and safety assessment of the inertially confined direct drive laser fusion power reactor SIRIUS-P

Environmental and safety analyses have been performed for SIRIUS-P, and its target factory and fuel reprocessing facilities. Both the C/C composite chamber and steel-reinforced concrete shield would easily qualify as Class A low level waste (LLW). Due to the high /sup 14/C activity, the Li/sub 2/O solid breeder and TiO/sub 2/ coolant would only qualify for Class C LLW. The radiological dose to the population in the vicinity of the reactor site due to the routine release of tritium is 0.56 mrem/yr. During a loss of coolant accident (LOCA) or loss of flow accident (LOFA), the whole body (WB) early dose at the site boundary (1 km) only amounts to 1.55 and 58.2 mrem for the chamber and shield, respectively. The WB early dose at the site boundary due to the Li/sub 2/O and TiO/sub 2/ are 93.5 /spl mu/rem and 93 mrem, respectively. A 100% release of the 156.3 g of tritium contained inside the reactor containment at any moment would produce a WB early dose on the order of 1.4 rem. Even though the target factory processes a total of 580,000 targets/day, the total tritium inventory along the production line is limited to only 285 g. The maximum WB early dose projected as a result of a severe accident involving the target factory of SIRIUS-P would be limited to 2.57 rem. In addition, a 100% release of the tritium contained in the fuel reprocessing facility would only result in a WB early dose of 640 mrem. The use of N-stamp nuclear grade components in SIRIUS-P can be avoided due to the low off-site doses.