The results concerning the irradiation embrittlement of WWER vessel materials prove the necessity of organizing experiments in controllable and adjustable conditions ensuring the unequivocal interpretation of the change of material properties under irradiation. The KORPUS facility for RBT-6 reactor was designed and made for the realization of controllable irradiation with the possibility of a simulation of reactor WWER vessel materials working conditions. The KORPUS design and technical characteristics are considered in this paper. Its experimental possibilities from the point of view of material testing and reactor dosimetry execution are discussed. The precomputation results indicative of possible simulation of vessel material working conditions are presented. The proposals on creating dosimetry experimental conditions are formulated.
Activity of templates (specimens), which were cut out from the inner surface of Kola-1 and Kola-2 WWER-440 reactor pressure vessels (RPVs), were measured, and the results were used to support the RPV dosimetry. Twelve weld and two base metal templates of Kola-1 RPV were cut out after 25 fuel cycles. Thirteen weld and two base metal templates of Kola-2 RPV were cut out after 24 fuel cycles. Probes were taken from four corners of each template for dosimetry measurements. Activity of 54Mn in each probe was measured and the average activity of template material was determined. Calculations were carried out in P3S8 approximation of discrete ordinates method using the DOORS 3.2 code package and BUGLE-96 nuclear data library. Calculated activities were compared with experimental ones. Neutron fluence (for neutrons with E>0.5 MeV) was calculated and calculation uncertainty evaluated based on the comparison of calculated and measured RPV templates activities and on some results of WWER-440 mock-up experiments carried out earlier on the reactor LR-0.
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