A.V. Tarbokov, M. Slobodyan, S. Pavlov, E. Smolyanskiy, D.G. Krotkevich, V. Ryzhkov, V. Uglov, G. Remnev
{"title":"高强度脉冲离子束预处理改善锆合金和奥氏体不锈钢防护涂层性能","authors":"A.V. Tarbokov, M. Slobodyan, S. Pavlov, E. Smolyanskiy, D.G. Krotkevich, V. Ryzhkov, V. Uglov, G. Remnev","doi":"10.56761/efre2022.c3-p-017602","DOIUrl":null,"url":null,"abstract":"The report discusses the influence of pre-treatment of metal substrates with a high-intense pulsed ion beam on functional properties of subsequently deposited protective coatings. Austenitic stainless steel and the Zr-1%Nb alloy have been studied, which are used in the nuclear industry as structural materials. The following irradiation parameters have been applied: the accelerating voltage of 200 kV, pulse duration of 90 ns, and the energy density per pulse of 1.5 J/cm2. After irradiation, coatings of both Fe-Cr-Al and Al-Si-N systems have been deposited by magnetron sputtering. Then, both normal and accidental losses of coolant conditions for water-cooled nuclear reactors are simulated. Radiation damage was modeled using 400 keV protons with a current density of 0.667 μA/cm2and a fluence of 2.25∙1016 proton/cm2. The second modeling method was the hydrogenation of samples – 360 °C, pressure of 2 atm for 2 hours. After irradiating the coatings with protons or saturating them with hydrogen, high-temperature oxidation of the samples was carried out in air and steam at a temperature of 1000 °C for 180 seconds. Finally, the oxidized samples have been studied by scratch tests and subsequent investigations using scanning electron microscopy in order to understand the effect of the pre-treatment procedure.","PeriodicalId":156877,"journal":{"name":"8th International Congress on Energy Fluxes and Radiation Effects","volume":"34 1","pages":"0"},"PeriodicalIF":0.0000,"publicationDate":"2022-11-14","publicationTypes":"Journal Article","fieldsOfStudy":null,"isOpenAccess":false,"openAccessPdf":"","citationCount":"0","resultStr":"{\"title\":\"Improvement properties of protective coatings on zirconium alloys and austenitic stainless steels by pre-treatment with high-intense pulsed ion beams\",\"authors\":\"A.V. Tarbokov, M. Slobodyan, S. Pavlov, E. Smolyanskiy, D.G. Krotkevich, V. Ryzhkov, V. Uglov, G. Remnev\",\"doi\":\"10.56761/efre2022.c3-p-017602\",\"DOIUrl\":null,\"url\":null,\"abstract\":\"The report discusses the influence of pre-treatment of metal substrates with a high-intense pulsed ion beam on functional properties of subsequently deposited protective coatings. Austenitic stainless steel and the Zr-1%Nb alloy have been studied, which are used in the nuclear industry as structural materials. The following irradiation parameters have been applied: the accelerating voltage of 200 kV, pulse duration of 90 ns, and the energy density per pulse of 1.5 J/cm2. After irradiation, coatings of both Fe-Cr-Al and Al-Si-N systems have been deposited by magnetron sputtering. Then, both normal and accidental losses of coolant conditions for water-cooled nuclear reactors are simulated. Radiation damage was modeled using 400 keV protons with a current density of 0.667 μA/cm2and a fluence of 2.25∙1016 proton/cm2. The second modeling method was the hydrogenation of samples – 360 °C, pressure of 2 atm for 2 hours. After irradiating the coatings with protons or saturating them with hydrogen, high-temperature oxidation of the samples was carried out in air and steam at a temperature of 1000 °C for 180 seconds. Finally, the oxidized samples have been studied by scratch tests and subsequent investigations using scanning electron microscopy in order to understand the effect of the pre-treatment procedure.\",\"PeriodicalId\":156877,\"journal\":{\"name\":\"8th International Congress on Energy Fluxes and Radiation Effects\",\"volume\":\"34 1\",\"pages\":\"0\"},\"PeriodicalIF\":0.0000,\"publicationDate\":\"2022-11-14\",\"publicationTypes\":\"Journal Article\",\"fieldsOfStudy\":null,\"isOpenAccess\":false,\"openAccessPdf\":\"\",\"citationCount\":\"0\",\"resultStr\":null,\"platform\":\"Semanticscholar\",\"paperid\":null,\"PeriodicalName\":\"8th International Congress on Energy Fluxes and Radiation Effects\",\"FirstCategoryId\":\"1085\",\"ListUrlMain\":\"https://doi.org/10.56761/efre2022.c3-p-017602\",\"RegionNum\":0,\"RegionCategory\":null,\"ArticlePicture\":[],\"TitleCN\":null,\"AbstractTextCN\":null,\"PMCID\":null,\"EPubDate\":\"\",\"PubModel\":\"\",\"JCR\":\"\",\"JCRName\":\"\",\"Score\":null,\"Total\":0}","platform":"Semanticscholar","paperid":null,"PeriodicalName":"8th International Congress on Energy Fluxes and Radiation Effects","FirstCategoryId":"1085","ListUrlMain":"https://doi.org/10.56761/efre2022.c3-p-017602","RegionNum":0,"RegionCategory":null,"ArticlePicture":[],"TitleCN":null,"AbstractTextCN":null,"PMCID":null,"EPubDate":"","PubModel":"","JCR":"","JCRName":"","Score":null,"Total":0}
Improvement properties of protective coatings on zirconium alloys and austenitic stainless steels by pre-treatment with high-intense pulsed ion beams
The report discusses the influence of pre-treatment of metal substrates with a high-intense pulsed ion beam on functional properties of subsequently deposited protective coatings. Austenitic stainless steel and the Zr-1%Nb alloy have been studied, which are used in the nuclear industry as structural materials. The following irradiation parameters have been applied: the accelerating voltage of 200 kV, pulse duration of 90 ns, and the energy density per pulse of 1.5 J/cm2. After irradiation, coatings of both Fe-Cr-Al and Al-Si-N systems have been deposited by magnetron sputtering. Then, both normal and accidental losses of coolant conditions for water-cooled nuclear reactors are simulated. Radiation damage was modeled using 400 keV protons with a current density of 0.667 μA/cm2and a fluence of 2.25∙1016 proton/cm2. The second modeling method was the hydrogenation of samples – 360 °C, pressure of 2 atm for 2 hours. After irradiating the coatings with protons or saturating them with hydrogen, high-temperature oxidation of the samples was carried out in air and steam at a temperature of 1000 °C for 180 seconds. Finally, the oxidized samples have been studied by scratch tests and subsequent investigations using scanning electron microscopy in order to understand the effect of the pre-treatment procedure.