Spent nuclear fuel from fluoride-salt-cooled high-temperature reactors presents different set of storage and handling challenges than fuel from light water reactors and requires the implementation of new strategies. This study explores potential strategies involving pool storage (in helium or FLiNaK) and cask storage/transportation in sequential phases and assesses the feasibility of such strategies in terms of thermal-hydraulics, criticality safety and radiation shielding. The most demanding constraints to the design of the pool storage system are set by criticality safety and require distributing the spent fuel in separate containers. Subcriticality of the fuel in the casks can be maintained by mixing boron-doped graphite spheres with the spent pebbles. High dose rates at the cask surface impede immediate loading of the pebbles in storage/ transportation casks, but the use of steel and lead based overpacks offers effective radiation shielding and good thermal properties, and allows loading spent fuel in the casks after as few as two years of pool storage.

来自氟化物盐冷却的高温反应堆的废核燃料与来自轻水反应堆的燃料相比，在储存和处理方面面临着不同的挑战，并且需要实施新的战略。这项研究探索了涉及池（在氦气或FLiNaK中）和桶在连续阶段中的存储/运输的潜在策略，并从热工液压，临界安全性和辐射屏蔽方面评估了此类策略的可行性。池存储系统设计最苛刻的限制是由临界安全性设置的，需要将用过的燃料分配到单独的容器中。通过将掺硼的石墨球与废卵石混合，可以保持燃料在桶中的亚临界状态。