Experimental testing of bellows compensators under conditions close to standard ones plays a key role in ensuring the reliability and safety of sodium-cooled nuclear reactors, such as the BN-1200 reactor plant. This scientific article discusses the development and implementation of a mock-up of a bellows compensator block (BSK mock-up) at a specialized SAZ stand, where the working section is located at +16.2 m and connected to a 325×12 mm bypass line pipeline through tees and shut-off valves at the inlet and outlet. For the safe conduct of acceptance tests, electrically operated shut-off valves are provided on the supply and outlet pipelines, which allows the system to be isolated if necessary. The BSK layout is equipped with a protective casing, in the lower part of which there is a sodium leak sensor such as an automobile spark plug, which provides early detection of leak proofness. The signal from the sensor is output to the operator’s console 1PO (room 205) in the form of a light and sound alarm «sodium flowing through the BSK layout», which contributes to rapid response and prevention of emergency situations. The test methodology includes modeling of standard conditions with sodium circulation at temperatures up to 550 °C, pressures up to 10 MPa and flow rates up to 100 m3/h, with static, dynamic and emergency tests to assess the tightness, fatigue strength and effectiveness of safety systems. The results demonstrate the high reliability of the BSK layout, with tightness under pressure up to 12 MPa, minimal deformations under cyclic loads and rapid operation of emergency systems, which confirms its suitability for incident prevention in the BN-1200 control room. Data analysis has revealed design optimization opportunities, reducing risks by 25 %, and highlights the integration of modern monitoring technologies for predictive maintenance. In conclusion, the experimental validation at the SAZ stand strengthens the safety of sodium reactors, contributing to the sustainable development of generation IV nuclear power and recommending further research using digital twins for virtual testing. This approach not only minimizes operational risks, but also increases the efficiency of liquid metal cooling systems, opening up new prospects for innovation in the field of nuclear engineering.