<p>This study presents a conceptual design of a 200&#xa0;MW plasma-jet-driven magneto-inertial fusion (PJMIF) reactor blanket, referring to fusion reactor technologies. The blanket employs a dual-coolant structure consisting of supercritical CO₂ and Li₁₇Pb₈₃ liquid blanket. This paper is the first neutronics and nuclear thermal study of a dual-coolant lead-lithium (DCLL) blanket for a PJMIF reactor. A complete nuclear analysis of the DCLL is carried out with the TopMC Monte Carlo transport and activation code. Transient coupled models are established to calculate the temperature distribution and variations with the blanket. Key objectives include: (1) determining optimized geometric parameters, including LiPb/steel thickness and radial build; (2) quantifying nuclear heating distributions and peak power density; (3) assessing tritium breeding ratio (TBR) using LiPb enrichment sensitivity; and (4) evaluating radiation damage in the spherical first wall and plasma gun. This study summarizes the distribution pattern of DPA in the inner electrode during the normal operation of the reactor, providing data for assessing the plasma gun’s lifespan. The research findings indicate that the nuclear thermal coupling model can complete preliminary calculations and analysis. It is found that both tritium production and energy export from the blanket are influenced by the reactor cavity and the breeding zone size. Under the 200&#xa0;MW operating conditions, it shows that a 3.8&#xa0;m radius and a 65&#xa0;cm breeding zone size best meet the requirements.</p>