Molten Salt Reactors (MSRs) are one of six Generation IV reactor designs currently under development around the world. Because of the unique operating conditions of MSRs, which include molten fuel and the continuous removal of gaseous fission products during operation, work was performed to model the production of activation and fission products and analyze the potential impact of emissions on the International Monitoring System (IMS) of the Comprehensive Nuclear-Test-Ban Treaty (CTBT). Simulations were performed to predict the production of IMS-relevant radionuclides in four MSR designs operating under two scenarios: (1) a sealed reactor with releases only during operational shutdown, and (2) continuous reprocessing or sparging of the fuel salt. From these production estimates the radioxenon and radioiodine signatures were extracted and compared to three current reactor designs (Boiling Water Reactor, Pressurized Water Reactor, High-Power Channel-Type Reactor). In cases where continuous reprocessing of the fuel salt occurred, both the radioxenon and radioiodine signatures were nearly indistinguishable from a nuclear explosion. Estimates were also made of the potential emission rate of radioxenon for three reactor designs and it was found that MSRs have the potential to emit radioxenon isotopes at a rate of ${10}^{15}-8\times {10}^{16}$ Bq/d for ¹³³Xe, which may adversely affect nuclear explosion monitoring, if no abatement is used. An assessment was made of activation products using a candidate fuel salt (FLiBe) mixed with corrosion products for the Thorium Molten Salt Reactor (TMSR-LF1).

熔融盐反应堆（MSR）是目前在全球范围内开发的六种第四代反应堆设计之一。由于MSR的独特运行条件，包括熔融燃料和在运行过程中不断去除气态裂变产物，因此开展了工作以对活化和裂变产物的产生进行建模，并分析了排放物对国际监测系统（IMS）的潜在影响。 《全面禁止核试验条约》（《全面禁试条约》））。进行了模拟，以预测在两种情况下运行的四种MSR设计中与IMS有关的放射性核素的产生：（1）密封反应堆仅在运行停机期间释放，以及（2）连续后处理或喷洒燃料盐。从这些生产估算中，提取了放射性氙和放射性碘的特征并将其与三种当前的反应堆设计（沸水反应堆，加压水反应堆，大功率通道型反应堆）进行了比较。在发生燃料盐的连续后处理的情况下，放射性氙和放射性碘的特征几乎与核爆炸没有区别。还对三种反应堆设计的放射性氙的潜在发射率进行了估算，发现MSR具有以5％的速率发射放射性氙同位素的潜力。${10}^{15}-8\times {10}^{16}$Bq / d为¹³³ Xe，如果不进行减排，可能会对核爆炸监测产生不利影响。使用activation燃料盐反应器（TMSR-LF1）的候选燃料盐（FLiBe）和腐蚀产物混合的活化产物进行了评估。