Improvement properties of protective coatings on zirconium alloys and austenitic stainless steels by pre-treatment with high-intense pulsed ion beams

8th International Congress on Energy Fluxes and Radiation Effects Pub Date : 2022-11-14 DOI:10.56761/efre2022.c3-p-017602

A.V. Tarbokov, M. Slobodyan, S. Pavlov, E. Smolyanskiy, D.G. Krotkevich, V. Ryzhkov, V. Uglov, G. Remnev

{"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}

引用次数: 0

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.

查看原文本刊更多论文

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

本文讨论了用高强度脉冲离子束预处理金属基底对随后沉积的保护涂层功能性能的影响。对核工业中用作结构材料的奥氏体不锈钢和Zr-1%Nb合金进行了研究。辐照参数为加速电压200 kV，脉冲持续时间90 ns，每脉冲能量密度1.5 J/cm2。辐照后，用磁控溅射法制备了Fe-Cr-Al和Al-Si-N体系的镀层。然后，对水冷核反应堆的正常和意外冷却剂损失情况进行了模拟。辐射损伤模型采用400 keV质子，电流密度为0.667 μA/cm2，影响为2.25∙1016质子/cm2。第二种建模方法是将样品加氢- 360°C, 2atm压力下加氢2小时。在用质子照射涂层或用氢使其饱和后，将样品在1000℃的空气和蒸汽中进行180秒的高温氧化。最后，通过划痕试验和随后的扫描电镜研究氧化样品，以了解预处理程序的影响。

本文章由计算机程序翻译，如有差异，请以英文原文为准。

求助全文

约1分钟内获得全文求助全文

来源期刊

8th International Congress on Energy Fluxes and Radiation Effects

自引率

0.00%

发文量