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Information × Registration Number 0221U104702, 0116U006287 , R & D reports Title Development of the generalized methodology and methodological recommendations for the calculation analysis of the stress state and fracture resistance to justify the strength and life extension of reactor pressure vessels and equipment elements of the WWER NPP primary circuit using the currently available methods for consideration of the defect presence and deformation history for the thermo-mechanical loading. popup.stage_title Head Kharchenko Valerii V., Доктор технічних наук Registration Date 06-04-2021 Organization GS Pisarenko Institute of Strength Problems of the National Academy of Sciences of Ukraine popup.description2 The authors have developed the generalized methodology and instructional guidelines of the refined computational analysis of the stress-strain state (SSS) kinetics, as well as fracture mechanics parameters of the nuclear plant primary system, in particular, WWER reactor pressure vessels, hot collector-to-nozzle welded joint in a PGV-1000 steam generator and internal vessel units (using baffle and barrel as examples). The methodology and guidelines considered the presence of defects during modeling the operational and emergency modes of loading to justify their strength and lifetime extension. These instructional guidelines allowed one to obtain the refined results of the calculations regarding the substantiation of the strength values of the nuclear plant primary system elements, as well as the analysis of the stress-strain state and fracture resistance of the cylindrical part and zone of DU850 nozzle in the WWER-1000 reactor pressure vessel, hot collector-to-nozzle welded joint in a PGV-1000 steam generator and elements of the in-vessel units – baffle and barrel. The Ukrainian organization standard SOU 56-47-2020 “Procedure of calculation of the stress-strain state and fracture resistance in reactor pressure vessels and elements of the NPP primary system equipment elements with WWER” has been developed using the instructional guidelines. This standard specifies the main requirements and recommendations regarding the complex refined calculations based on the finite element methods of SSS and fracture resistance in the WWER-1000 reactor pressure vessels, hot header-to-PGV-1000M steam generator connector weldment, baffle and in-vessel barrel with the postulated defects during modeling of the operational and emergency loading modes. Product Description popup.authors popup.nrat_date 2021-04-06 Close