Abstract: In order to further enhance the positioning precision and operational stability of the control rod drive system applied in pool-type low-temperature nuclear heating reactors, this paper conducted a comprehensive experimental investigation on the overall operating performance of the self-developed control rod hydraulic drive system (CRHDS). Based on the actual hydraulic operating parameters of the prototype low-temperature heating reactor, a 1∶1 equivalent test system was established to fully reproduce the internal hydraulic transmission circuit, the transmission relationship of the traction mechanism and full-stroke movement process of the control rod in CRHDS, which accurately restores the actual hydraulic load and dynamic motion characteristics of the device under real operating conditions. A dedicated cold-state experimental bench matching the structural parameters and operating characteristics of the CRHDS was constructed to simulate the actual operating environment of the reactor under normal working conditions. The operating characteristics of the system under variable inlet pressure conditions and the dynamic performance during typical rapid rod drop working conditions were systematically tested, while the generation mechanism of system displacement deviation and the hydraulic buffer characteristics in the rod drop process were emphatically analyzed and summarized. The experimental results indicate that the system exhibits uniform pressure variation rules and excellent dynamic response stability during the control rod lifting and inserting processes under different inlet pressure conditions, which verifies the superior self-adjusting performance of the hydraulic drive system. The minor displacement offset occurring in the rod movement process is primarily derived from the elastic deformation of the traction rope, and the adaptive adjustment of the internal throttle port will not interfere with the final positioning accuracy of the control rod. The steel wire rope flexible connection structure adopted by the system can effectively eliminate the elastic displacement error generated in the operation process, which is feasible to replace the traditional rigid connection mode of conventional control rod drive mechanisms. The device is equipped with a porous hydraulic buffer structure, which realizes rod drop deceleration through the synergistic effect of elastic energy storage of springs and energy dissipation via fluid throttling. Meanwhile, the CRHDS realizes stable and smooth rapid rod drop movement with excellent hydraulic buffering effect, which fully satisfies the safe operation demands of low-temperature heating reactors. The research conclusions obtained in this study can provide solid experimental reference and effective technical support for the subsequent engineering optimization and practical application of control rod hydraulic drive technology for pool-type low-temperature nuclear heating reactors.