Search academic texts

Information × Registration Number 0211U004051, 0109U006544 , R & D reports Title The development of technology of receiving of zirconium and zirconium alloys with high resistance of absorption of hydrogen popup.stage_title Head Cherniy Bogdan, Registration Date 20-01-2011 Organization State Scientific-Produkction peant "Rubin" of NAS of Ukraine popup.description2 Iodide zirconium, iodide zirconium alloys with platinum and alloy CТZ 110 alloyed by platinum and rhodium are object of research. Research objective - development of experimental technology for receiving of surface and near-surface layers with the raised resistance to hydrogen penetration on zirconium and zirconium alloys by electrotreatment method. Research methods are experimental. The experimental technique of electric-discharge processing of zirconium and its alloys is developed. This technique allows to carry out cathodic and anodic processing of samples in a water solution of chloroplatinic acid with "metal-metal" electrodes system. The comparison tests of samples of zirconium and its alloys in hydrogen atmosphere under pressure of 1 bar and at temperatures 400 and 500 С had been realized. The main practical results are the following: for the first time it is shown that iodide zirconium samples after cathodic processing and the subsequent oxidation in air atmosphere during 32 hours of test absorb hydrogen in 3 times less, than the deformed source samples, and at 500 С ? in 1,2 times. The comparison tests of CТZ 110 alloys in hydrogen atmosphere at temperatures 400 and 500 С were carried out. After cathodic-anodic processing the alloys for 15 hours of test absorb hydrogen by 25 % less, than source metal. After electric-discharge processing of КТЦ 110 alloy alloyed Pt + Rh the resistance to hydrogen at Т = 400 С increases in 1,7 times. Complex processing of (КТЦ 110 + 0,13 mass percent of Pt) alloy reduces hydrogen absorption by 50 % during 16 hours test at 400 С. Analogs of similar developments are not in Ukraine. The work results can be used for developing of materials for the containers intended for transportation and storage of radioactive waste and materials, as well as for increase of corrosion resistance of an external surface of a cover of fuel pin of a zirconium alloy. Product Description popup.authors Зейдлиць Михайло Петрович Клінчук Юрій Іванович popup.nrat_date 2020-04-02 Close