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Information × Registration Number 0216U002339, 0113U005931 , R & D reports Title Development and realization on power units of WWER-1000 of NPS of Ukraine of modern methods of diagnostic monitoring of technical state of the metal of rector vessel and pipe-lines popup.stage_title Head Ozhigov Leonid Semenovich, Registration Date 18-02-2016 Organization National Science Center "Kharkiv Institute of Physics and Technology popup.description2 Report on SRW: pages - 95, figures - 66, tables - 4, references -18. Metal of welded joint #111 of collector welding to branch pipe DU-1200 of steam generator PGV-1000 and of welded joints of pipe-lines of binding ChZVK of power units #1-3 in reactor WWER-1000 in SUNPS was investigated by methods of coercimetery and magnetic memory of the metal. The good correlation of data obtained by two magnetic methods is proved. The reliability of magnetic methods is confirmed by ultrasound and radiography study of the metal. Recommendation on joint use of magnetic methods is proposed; this will give objective and total information on real state of the base metal and welded joints of pipe-lines of NPS power units. On the base of static treatment of data base VSK which is annually expanded the plans of future measurement are drawn up and on the base of accumulated data the dependencies of the process of defect production in steam generator pipes on the factor of sludge deposition are revealed. On the base of micro X-ray electron probe, X-ray fluorescence methods and scanning electron microscopy the element composition and morphology of sludge deposition was determined in the area of welded joint obtained under repair of collector joining with steam generator (joint #111) on power unit of SU NPS. The presence of particles of free copper into the sludge was shown; on the base of this the reasons of pitting and further corrosion cracking of the metal of welded joints of second circuit. Methodology and modulus of remote determination of residual stresses and characteristics of the metal of outer surface of reactor pressure vessel of power unit of WWER-1000 are developed. The operation of the modulus is based on the submersion of hardness-tester ball into the body of reactor pressure vessel and on the recording of the results of this submersion by interferometer. The operating model of the modulus was produced and its adjustment in laboratory conditions and on stands of SU NPS was carried out. Key words: eddy current control, defects, welded joint, coercimetery, corrosion, magnetic memory of the metal, optical - mechanical modulus, steam generator, cracking, pipe-still, sludge depositions. Product Description popup.authors Василенко Руслан Леонідович Воєводін Вііктор Миколайович Волчок Олег Йосипович Гоженко Сергій Васильович Крайнюк Євген Олександрович Лісна Валентина Георгіцївна Міщенко Павло Олександрович Митрофанов Анатолій Сергійович Неклюдов Іван Матвійович Ожигов Леонід Семенович Петухов Валентин Вікторович Руденко Олексій Генадійович Ружицький Валерій Володимирович Савченко Володимир Іванович Толстолуцька Галина Дмитрівна Шаповал Іван Миколайович Шрамченко Сергій Васильович popup.nrat_date 2020-04-02 Close