Molten salt reactor is one of the six internationally recognized and recommended fourth generation reactors that can use liquid nuclear fuel. The production, transportation, and storage of nuclear fuel involve different processes from conventional solid-state nuclear fuel reactors.

This study aims to perform criticality safety analysis for nuclear fuel storage of molten salt reactor in compliant with requirements of nuclear fuel management and nuclear safety supervision.

The design parameters of MSRE (Molten Salt Reactor Experiment) were referred for criticality safety analysis, and the impact of different factors on nuclear fuel salt storage was analyzed. Calculation was completed by selecting storage modeling, critical parameter analysis, and Monte Carlo neutron transport software simulation for liquid fuel molten salt reactor nuclear fuel. The k_eff values of dry environment storage and water flooded environment storage under the design model were summarized, so did the changes in the total mass of fuel salt.

The quality of subcritical safety control under different conditions are obtained and compared with corresponding raw material salts, intermediate products, and consideration of container walls. This study combines legal regulations and the process of nuclear material circulation for analysis and discussion, summarizes the critical safety characteristics of nuclear fuel salt, and for the first time proposes relevant supervision and evaluation points from the perspective of nuclear safety supervision.