Johnson Christine, Slack Johnathan L, Sharma Manish K, Simpson Cheslan K, Burnett Jonathan L
Pacific Northwest National Laboratory, Richland, WA, USA.
Pacific Northwest National Laboratory, Richland, WA, USA.
J Environ Radioact. 2021 Aug;234:106625. doi: 10.1016/j.jenvrad.2021.106625. Epub 2021 May 3.
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 10-8×10 Bq/d for Xe, 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).
熔盐反应堆(MSR)是目前全球正在研发的六种第四代反应堆设计之一。由于熔盐反应堆的独特运行条件,包括熔融燃料以及运行期间气态裂变产物的持续去除,因此开展了相关工作来模拟活化产物和裂变产物的生成,并分析排放物对《全面禁止核试验条约》(CTBT)国际监测系统(IMS)的潜在影响。进行了模拟,以预测在两种情景下运行的四种熔盐反应堆设计中与IMS相关的放射性核素的生成情况:(1)一个仅在运行停机期间有释放的密封反应堆,以及(2)燃料盐的连续后处理或鼓泡。根据这些生成量估计,提取了放射性氙和放射性碘特征,并与三种当前反应堆设计(沸水反应堆、压水反应堆、大功率通道型反应堆)进行了比较。在燃料盐进行连续后处理的情况下,放射性氙和放射性碘特征与核爆炸几乎无法区分。还对三种反应堆设计的放射性氙潜在排放率进行了估计,结果发现,如果不采取减排措施,熔盐反应堆有可能以10-8×10 Bq/d的速率排放氙的放射性同位素,这可能会对核爆炸监测产生不利影响。使用一种候选燃料盐(FLiBe)与钍基熔盐反应堆(TMSR-LF1)的腐蚀产物混合,对活化产物进行了评估。