This paper provides an overview of the current MSR design space and lists unique features of the various designs under consideration. Some general considerations for source terms calculation for Molten Salt Reactors (MSRs) are explained. Applicability and limitations of terminology currently defined for legacy light water reactor (LWR) systems are discussed in the view of MSRs and the need for updated terminology is discussed. Calculations carried out for the Molten Salt Reactor Experiment (MSRE) are discussed with a qualitative comparison to the designs presented. The nature of the fission products (FPs) and actinides for Low enriched uranium, thorium and fast U/Pu fuel cycles employed in representative molten salt reactor systems are discussed. Computational results are obtained from a code (Serpent 2) with online reprocessing. Divergence in source terms when fission product bubbling is demonstrated. The source release for each molten salt reactor during postulated accidents is also presented.

本文概述了当前的MSR设计空间，并列出了所考虑的各种设计的独特功能。解释了熔融盐反应堆（MSR）的源术语计算的一些一般注意事项。从MSR的角度讨论了当前为遗留轻水反应堆（LWR）系统定义的术语的适用性和局限性，并讨论了对更新术语的需求。讨论了熔盐反应器实验（MSRE）进行的计算，并对所提出的设计进行了定性比较。讨论了用于代表性熔盐反应堆系统中的低浓铀，or和快速U / Pu燃料循环的裂变产物（FPs）和act系元素的性质。计算结果是从具有在线重新处理的代码（Serpent 2）获得的。当裂变产物起泡被证明时，在来源方面存在分歧。还列出了假设事故期间每个熔融盐反应堆的排放源。