Reprocessing separation efficiency (RSE) is one important fuel cycle indicator which determines the loss of actinides left in the nuclear waste and the recovered actinides for reuse in the core, affecting the nuclear waste management, fuel utilization and other fuel cycle characteristics. By changing the reprocessing cycle time (RCT) from 10 days to 360 days, the impacts of RSE varying from 99.9% to 99.999% on the core actinides inventory evolution, breeding ratio (BR) and nuclear waste radiotoxicity were investigated for a Heavy Water moderated Molten Salt Reactor (HWMSR), which is a newly proposed molten salt reactor (MSR) that adopts heavy water rather than graphite as the moderator while employs the usual liquid fuel as in a traditional MSR. The obtained results demonstrate that the inventories of transuranic (TRU) and uranium except U-233 at equilibrium and their transition time to equilibrium both decreases as RSE declines due to their increased mass loss in reprocessing, which in turn brings down the parasitic neutron absorption in the core. Consequently, the U-233 inventory required for maintaining critical operation for a lower RSE drops. While the Th-232 inventory rises, since it is online refueled to maintain the total heavy metal (HM) content in the core constant to ensure the electrochemical stability of the fuel salt. As a result, BR is relatively improved as RSE decreases. But the increased U-233 production resulting from the improved BR could not compensate for the U-233 loss during reprocessing and leads to a longer doubling time for a lower RSE. The radiotoxicity of nuclear waste increases as RSE decreases since more actinides are lost to the nuclear waste. The above effects caused by RSE are mitigated as the RCT prolongs since the frequency for reprocessing the fuel salt of primary loop over a given period decreases, leading to a decrease of HM loss. For an RSE level of 99.9%, the shortest doubling time appears at the RCT of 30 days rather than 10 days because the mitigation of U-233 loss overwhelms the efficiency decrease of FPs removal and Pa-233 extraction. By balancing the Th-U breeding and radiotoxicity, an RCT of 60 days is recommended for HWMSR for the RSE of 99.9%.

后处理分离效率（RSE）是一项重要的燃料循环指标，它决定了核废料中残留的锕系元素的损失和回收的锕系元素在堆芯中再利用，影响核废料管理、燃料利用和其他燃料循环特性。通过将后处理循环时间 (RCT) 从 10 天更改为 360 天，研究了重水缓和的 RSE 从 99.9% 到 99.999% 对核心锕系元素存量演变、繁殖率 (BR) 和核废料放射性毒性的影响熔盐反应堆（HWMSR）是一种新提出的熔盐反应堆（MSR），它采用重水而不是石墨作为慢化剂，同时使用传统MSR中常用的液体燃料。获得的结果表明，超铀 (TRU) 和除 U-233 之外的平衡铀的存量及其平衡过渡时间都随着 RSE 的下降而减少，因为它们在后处理中的质量损失增加，这反过来又降低了寄生中子吸收核心。因此，维持关键操作以降低RSE所需的U-233库存下降。在Th-232库存增加的同时，由于其在线加油以保持堆芯中总重金属（HM）含量恒定，以确保燃料盐的电化学稳定性。因此，随着 RSE 降低，BR 相对提高。但是由改进的 BR 导致的 U-233 产量增加无法弥补后处理过程中 U-233 的损失，并导致更长的倍增时间和更低的 RSE。核废料的放射性毒性随着 RSE 的降低而增加，因为更多的锕系元素会流失到核废料中。随着RCT的延长，由RSE引起的上述影响得以缓解，这是因为在给定时间段内对主回路燃料盐进行再处理的频率降低，从而导致HM损失降低。对于 99.9% 的 RSE 水平，最短的倍增时间出现在 30 天而不是 10 天的 RCT 中，因为 U-233 损失的减轻压倒了 FP 去除和 Pa-233 提取的效率下降。通过平衡 Th-U 繁殖和放射性毒性，建议 HWMSR 进行 60 天的 RCT，RSE 为 99.9%。RSE 引起的上述影响随着 RCT 的延长而减轻，因为在给定时间段内对主回路燃料盐进行再处理的频率降低，从而导致 HM 损失减少。对于RSE为99.9％的情况，最短的加倍时间出现在RCT上为30天而不是10天，因为减轻U-233损失压倒了FP去除和Pa-233提取效率的降低。通过平衡 Th-U 繁殖和放射性毒性，建议 HWMSR 进行 60 天的 RCT，RSE 为 99.9%。RSE 引起的上述影响随着 RCT 的延长而减轻，因为在给定时间段内对主回路燃料盐进行再处理的频率降低，从而导致 HM 损失减少。对于 99.9% 的 RSE 水平，最短的倍增时间出现在 30 天而不是 10 天的 RCT 中，因为 U-233 损失的减轻压倒了 FP 去除和 Pa-233 提取的效率下降。通过平衡 Th-U 繁殖和放射性毒性，建议 HWMSR 进行 60 天的 RCT，RSE 为 99.9%。