Search academic texts

Information × Registration Number 0220U000324, 0118U005263 , R & D reports Title Development of requirements and methodical recommendations for determining the stress and boundary condition of NPP's reactor pressure vessel elements and the 1st circuit equipment when substantiating their strength and life-time popup.stage_title Head Kharchenko Valeriy V., Доктор технічних наук Registration Date 29-01-2020 Organization Institute for problems of strength NASci of Ukraine popup.description2 The authors present the requirements and methodical recommendations on the determination of the stress and limit state of the first circuit equipment elements of NPP, in particular, of the WWER-1000 reactor pressure vessels, weldment of the heat header to the steam generator PGV-1000M, as well as the compartments and shafts of the WWER-1000 reactor pressure vessel in the modeling of operational and emergency load modes. The requirements and recommendations on the experimental determination of the temperature dependence of the fracture toughness are formulated taking into account the stochastic nature of the stress intensity distribution along the postulated crack front (scale effect), the effect of short cracks, and load duality. The methodological recommendations can be used by the NNEGC "Energoatom" of Ukraine in the improvement of the normative documents on the substantiation of the strength and fracture resistance of the equipment of the NPP first circuit. Product Description popup.authors Кобельський Сергій Володимирович Кондряков Євген Олександрович Котляренко Андрій Аркадійович Кравченко Віктор Іванович Сидяченко В'ячеслав Григорович Харченко Валерій Володимирович Чирков Олександр Юрійович popup.nrat_date 2020-04-02 Close