Preparation and characterization of Er^sub 2^O^sub 3^-ZrO^sub 2^ multi-layer coating for tritium permeation barrier by metal organic decomposition
Tritium permeation barrier coatings have been investigated for several decades to control tritium migration in fusion reactor fuel systems. In liquid lithium-lead blanket concepts, mitigation of not only tritium permeation through but also corrosion of structural materials is seriously required. In...
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Veröffentlicht in: | Fusion engineering and design 2018-11, Vol.136, p.219 |
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creator | Mochizuki, Jumpei Horikoshi, Seira Fujita, Hikari Matsunaga, Moeki Hishinuma, Yoshimitsu Oya, Yasuhisa Chikada, Takumi |
description | Tritium permeation barrier coatings have been investigated for several decades to control tritium migration in fusion reactor fuel systems. In liquid lithium-lead blanket concepts, mitigation of not only tritium permeation through but also corrosion of structural materials is seriously required. In this study, for the development of a multifunctional coating, Er2O3-ZrO2 multi-layer coatings were prepared on reduced activation ferritic/martensitic steel substrates by metal organic decomposition. The deuterium permeability of the coated sample was three orders of magnitude lower than that of uncoated substrate in the first permeation experiment at 400 °C, and the high permeation reduction was kept in the temperature range of 400–650 °C. The coatings remained all over the sample surface after Li-Pb immersion experiments at 500–600 °C for 500 h, but were damaged at 600 °C. No reduction in coating thickness was confirmed after immersion at 550 °C by cross-sectional observation, suggesting that the multi-layer coatings may be applicable to the liquid lithium-lead blankets. |
doi_str_mv | 10.1016/j.fusengdes.2018.01.059 |
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In liquid lithium-lead blanket concepts, mitigation of not only tritium permeation through but also corrosion of structural materials is seriously required. In this study, for the development of a multifunctional coating, Er2O3-ZrO2 multi-layer coatings were prepared on reduced activation ferritic/martensitic steel substrates by metal organic decomposition. The deuterium permeability of the coated sample was three orders of magnitude lower than that of uncoated substrate in the first permeation experiment at 400 °C, and the high permeation reduction was kept in the temperature range of 400–650 °C. The coatings remained all over the sample surface after Li-Pb immersion experiments at 500–600 °C for 500 h, but were damaged at 600 °C. No reduction in coating thickness was confirmed after immersion at 550 °C by cross-sectional observation, suggesting that the multi-layer coatings may be applicable to the liquid lithium-lead blankets.</description><identifier>ISSN: 0920-3796</identifier><identifier>EISSN: 1873-7196</identifier><identifier>DOI: 10.1016/j.fusengdes.2018.01.059</identifier><language>eng</language><publisher>Amsterdam: Elsevier Science Ltd</publisher><subject>Coatings ; Corrosion ; Decomposition ; Deuterium ; Erbium oxide ; Ferritic stainless steels ; Fuel systems ; Lead ; Liquid lithium ; Martensitic stainless steels ; Migration ; Multilayers ; Nuclear fuels ; Penetration ; Protective coatings ; Reactors ; Reduction ; Submerging ; Substrates ; Tritium ; Zirconium dioxide</subject><ispartof>Fusion engineering and design, 2018-11, Vol.136, p.219</ispartof><rights>Copyright Elsevier Science Ltd. 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In liquid lithium-lead blanket concepts, mitigation of not only tritium permeation through but also corrosion of structural materials is seriously required. In this study, for the development of a multifunctional coating, Er2O3-ZrO2 multi-layer coatings were prepared on reduced activation ferritic/martensitic steel substrates by metal organic decomposition. The deuterium permeability of the coated sample was three orders of magnitude lower than that of uncoated substrate in the first permeation experiment at 400 °C, and the high permeation reduction was kept in the temperature range of 400–650 °C. The coatings remained all over the sample surface after Li-Pb immersion experiments at 500–600 °C for 500 h, but were damaged at 600 °C. No reduction in coating thickness was confirmed after immersion at 550 °C by cross-sectional observation, suggesting that the multi-layer coatings may be applicable to the liquid lithium-lead blankets.</description><subject>Coatings</subject><subject>Corrosion</subject><subject>Decomposition</subject><subject>Deuterium</subject><subject>Erbium oxide</subject><subject>Ferritic stainless steels</subject><subject>Fuel systems</subject><subject>Lead</subject><subject>Liquid lithium</subject><subject>Martensitic stainless steels</subject><subject>Migration</subject><subject>Multilayers</subject><subject>Nuclear fuels</subject><subject>Penetration</subject><subject>Protective coatings</subject><subject>Reactors</subject><subject>Reduction</subject><subject>Submerging</subject><subject>Substrates</subject><subject>Tritium</subject><subject>Zirconium dioxide</subject><issn>0920-3796</issn><issn>1873-7196</issn><fulltext>true</fulltext><rsrctype>article</rsrctype><creationdate>2018</creationdate><recordtype>article</recordtype><recordid>eNqNjM1OwzAQhC0EEuHnGViJc4ydKEl9RkXcyqEnDqmcZBMcJXZY24fyGDwxgfYBkEYazey3w9iDFFwKWT6NvI8e7dCh55mQGy4kF4W6YIncVHlaSVVeskSoTKR5pcprduP9KISsViXs-41w0aSDcRa07aD9WFMbkMzXqXQ9bKn2sYGs3v15XqfvtDtXMMcpmHTSRyRo3fpjB-gdQSATTJxhQZrxNNVoIrNizRFmDHoCR4O2poUOWzcvzptf7I5d9XryeH_2W_b4st0_v6YLuc-IPhxGF8mup0MmC6VyWQiV_4_6AaEXYXk</recordid><startdate>20181101</startdate><enddate>20181101</enddate><creator>Mochizuki, Jumpei</creator><creator>Horikoshi, Seira</creator><creator>Fujita, Hikari</creator><creator>Matsunaga, Moeki</creator><creator>Hishinuma, Yoshimitsu</creator><creator>Oya, Yasuhisa</creator><creator>Chikada, Takumi</creator><general>Elsevier Science Ltd</general><scope>7TB</scope><scope>8FD</scope><scope>FR3</scope><scope>H8D</scope><scope>KR7</scope><scope>L7M</scope></search><sort><creationdate>20181101</creationdate><title>Preparation and characterization of Er^sub 2^O^sub 3^-ZrO^sub 2^ multi-layer coating for tritium permeation barrier by metal organic decomposition</title><author>Mochizuki, Jumpei ; Horikoshi, Seira ; Fujita, Hikari ; Matsunaga, Moeki ; Hishinuma, Yoshimitsu ; Oya, Yasuhisa ; Chikada, Takumi</author></sort><facets><frbrtype>5</frbrtype><frbrgroupid>cdi_FETCH-proquest_journals_21599315093</frbrgroupid><rsrctype>articles</rsrctype><prefilter>articles</prefilter><language>eng</language><creationdate>2018</creationdate><topic>Coatings</topic><topic>Corrosion</topic><topic>Decomposition</topic><topic>Deuterium</topic><topic>Erbium oxide</topic><topic>Ferritic stainless steels</topic><topic>Fuel systems</topic><topic>Lead</topic><topic>Liquid lithium</topic><topic>Martensitic stainless steels</topic><topic>Migration</topic><topic>Multilayers</topic><topic>Nuclear fuels</topic><topic>Penetration</topic><topic>Protective coatings</topic><topic>Reactors</topic><topic>Reduction</topic><topic>Submerging</topic><topic>Substrates</topic><topic>Tritium</topic><topic>Zirconium dioxide</topic><toplevel>peer_reviewed</toplevel><toplevel>online_resources</toplevel><creatorcontrib>Mochizuki, Jumpei</creatorcontrib><creatorcontrib>Horikoshi, Seira</creatorcontrib><creatorcontrib>Fujita, Hikari</creatorcontrib><creatorcontrib>Matsunaga, Moeki</creatorcontrib><creatorcontrib>Hishinuma, Yoshimitsu</creatorcontrib><creatorcontrib>Oya, Yasuhisa</creatorcontrib><creatorcontrib>Chikada, Takumi</creatorcontrib><collection>Mechanical & Transportation Engineering Abstracts</collection><collection>Technology Research Database</collection><collection>Engineering Research Database</collection><collection>Aerospace Database</collection><collection>Civil Engineering Abstracts</collection><collection>Advanced Technologies Database with Aerospace</collection><jtitle>Fusion engineering and design</jtitle></facets><delivery><delcategory>Remote Search Resource</delcategory><fulltext>fulltext</fulltext></delivery><addata><au>Mochizuki, Jumpei</au><au>Horikoshi, Seira</au><au>Fujita, Hikari</au><au>Matsunaga, Moeki</au><au>Hishinuma, Yoshimitsu</au><au>Oya, Yasuhisa</au><au>Chikada, Takumi</au><format>journal</format><genre>article</genre><ristype>JOUR</ristype><atitle>Preparation and characterization of Er^sub 2^O^sub 3^-ZrO^sub 2^ multi-layer coating for tritium permeation barrier by metal organic decomposition</atitle><jtitle>Fusion engineering and design</jtitle><date>2018-11-01</date><risdate>2018</risdate><volume>136</volume><spage>219</spage><pages>219-</pages><issn>0920-3796</issn><eissn>1873-7196</eissn><abstract>Tritium permeation barrier coatings have been investigated for several decades to control tritium migration in fusion reactor fuel systems. In liquid lithium-lead blanket concepts, mitigation of not only tritium permeation through but also corrosion of structural materials is seriously required. In this study, for the development of a multifunctional coating, Er2O3-ZrO2 multi-layer coatings were prepared on reduced activation ferritic/martensitic steel substrates by metal organic decomposition. The deuterium permeability of the coated sample was three orders of magnitude lower than that of uncoated substrate in the first permeation experiment at 400 °C, and the high permeation reduction was kept in the temperature range of 400–650 °C. The coatings remained all over the sample surface after Li-Pb immersion experiments at 500–600 °C for 500 h, but were damaged at 600 °C. No reduction in coating thickness was confirmed after immersion at 550 °C by cross-sectional observation, suggesting that the multi-layer coatings may be applicable to the liquid lithium-lead blankets.</abstract><cop>Amsterdam</cop><pub>Elsevier Science Ltd</pub><doi>10.1016/j.fusengdes.2018.01.059</doi></addata></record> |
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subjects | Coatings Corrosion Decomposition Deuterium Erbium oxide Ferritic stainless steels Fuel systems Lead Liquid lithium Martensitic stainless steels Migration Multilayers Nuclear fuels Penetration Protective coatings Reactors Reduction Submerging Substrates Tritium Zirconium dioxide |
title | Preparation and characterization of Er^sub 2^O^sub 3^-ZrO^sub 2^ multi-layer coating for tritium permeation barrier by metal organic decomposition |
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