Calculation and experimental studies for substantiating the design of BREST-OD-300 reactor sampler

The paper considers the development of an innovative lead coolant sampling device for the BREST-OD-300 pilot demonstration fast neutron reactor developed in the Russian Federation within the framework of the Generation IV international initiative. The sampler is equipped with a lateral inclined channel located above the level of the lead coolant and a curved section for sampling both at an operating reactor and in a shutdown mode. The sampler design is protected by two patents of the Russian Federation. The results of tests on loading/unloading a capillary transport tube into a curved sampling channel and the reverse operation are considered. Moreover, the paper presents the results of tests on filling a sampling capsule with a lead coolant sample and its holding during removal from the reactor. The software of the sampler control system was tested for automatic sampling. The performance of the designed sampler is additionally confirmed by thermal engineering, strength, and radiation calculations.