ENVIRONMENTAL AND SAFETY ASSESSMENT OF LIBRA-SP - A LIGHT-ION FUSION POWER-REACTOR DESIGN

LIBRA-SP is a 1000 MWe light ion beam power reactor design study. The reactor structure is made of a low activation ferritic steel and uses LiPb as a breeder. The total activities in the blanket and reflector a t shutdown are 721 MCi and 924 MCi, respectively. Rands-on maintenance is impossible anywhere inside the reactor chamber. The biological dos e rates near the diode are too high at all times following shutdown al lowing only for remote maintenance. The blanket and reflector could qu alify for disposal as Class C low level waste. The dose to the maximal ly exposed individual in the vicinity of the reactor site due to the r outine release of tritium is about 2.39 mrem/yr. Ten hours after a los s of coolant accident, the reflector produces a whole body (WB) early dose at the site boundary of 253 mrem. The blanket would produce a WB early dose of 8.91 rem. The potential off-site dose produced by the mo bilization of LiPb during an accident is 142 mrem. A 100% release of t he vulnerable tritium inventory present in the containment at any mome nt results in a WB early dose of 459 mrem. Release of the vulnerable t ritium inventories present in the target factory and fuel reprocessing facility during an accident would result in WE early doses of 1.3 and 0.95 rem, respectively.