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Information × Registration Number 0213U007418, 0110U004281 , R & D reports Title Introductiion of efficient nondestructive inspection techniques at nuclear power plant units of Ukraine for estimating strain-stress distribution and remaining life of reactor vessels and pipelines. popup.stage_title Head Ozhigov Leonid Semenovich, Registration Date 23-10-2013 Organization National Science Center "Kharkiv Institute of Physics and Technology popup.description2 Report on SRW: pages - 80, fig.-100, tables - 3, references - 9. Subject of research : Base metal and welded joints of equipment and pipe-lines of NPS power-generating units. Purpose of the work: Carrying out of the work on power generating units of NPS of Ukraine for diagnostic monitoring of properties changes in base material and in welded joint during long-term operation for substantiation of safety of pressure-vessels and pipe-lines during their operation in designed term and on life extension. Development of new effective methods for life control of metal for base equipment and pipe-lines of power-generating units of NPS. Method of research: Works were carried out by the method of magnetic memory, of coercimetry and by the method of finite elements. Main results: To order of VP SU NPS works for development, fabrication and testing of equipment for cutting out of template from pressure vessel of reactor WWER-1000 were performed. Technology and regimes of template cutting-out in conditions of special pressure vessel of SU NPS are developed with the use of the system CK-187MY.Cutting-out of template from simulator of reactor pressure vessel in SU NPS is realized. Unit for the removal of stress concentrator was developed, produced and tested. Technology of the surface polishing was developed with the use of the system CK-187MJ in SU NPS. Surface polishing for the removal of stress concentrators was performed with remote control. Possibilities of digital interferometer for determination of residual stresses of the base metal and of welded joints of operating reactor are analyzed. Circuit of the module for diagnostic control of stresses in pressure vessel of reactor WWER-1000is developed. Changes of quenching stresses in pipe-line pattern in the result of magnetic treatment are studied. It is shown that it is possible to change the position of the zone of maximum stresses by the magnetic treatment in pipe-lines. Works for magnetic control of welded joint N 111 are performed on power-generating units of SU NPS and ZNPS. It is shown that at realization of control succession the data of measurement by the method of magnetic memory correlate with the data of coercimetry and complete one another. Data base of eddy current control of the steam generator pipe still for power generating units of WWER-1000 is expanded (more than 1,1 mln of measurements). Finite element patterns of critical elements of power generator PGV-1000M of heat-exchanging tubes with local defect are produced. Stress-deformed state of critical elements in static and dynamic conditions of operation is analyzed. Key words: NPS, pressure vessel of reactor, welded joints, magnetic memory, stress-deformed state, method of finite elements, heat-exchange tube, template, rigid electrode. Product Description popup.authors Ажажа Жана Сергіївна Воєводін Віктор Миколайович Волчок Олег Йосипович Гоженко Сеергій Васильович Крайнюк Євген Олександрович Лісна Валентина Георгіївна Міщенко Павло Олександрович Мац Олександр Владиславович Неклюдов Іван Матвійович Ожигов Леонід Семенович Пєтухов Валентин Вікторович Руденко Олексій Генадійович Савченко Володимир Іванович Соколенко Володимир Іванович Тальянская Ольга Яківна Черняк Микола Олексійович Шаповал Іван Миколайович Шрамченко Сергій Васильович popup.nrat_date 2020-04-02 Close