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High-temperature tribological behavior of structural materials after conditioning in impure-helium environments for high-temperature gas-cooled reactor applications
Incoloy 800HT and Inconel 617 have been selected as candidate structural alloys for the high-temperature gas-cooled reactor (HTGR) concept. Helium, the primary coolant, contains impurities (e.g., H2O and CH4) that can induce corrosion reactions at high temperatures, which in turn can affect the trib...
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Published in: | Journal of nuclear materials 2019-08, Vol.522, p.311-323 |
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description | Incoloy 800HT and Inconel 617 have been selected as candidate structural alloys for the high-temperature gas-cooled reactor (HTGR) concept. Helium, the primary coolant, contains impurities (e.g., H2O and CH4) that can induce corrosion reactions at high temperatures, which in turn can affect the tribological behavior of components in sliding contact such as valves and control-rod drive systems. This paper presents results from the study of the tribological behavior of both alloys before and after conditioning them in either an impure-helium oxidizing environment or in an air environment. Both alloys were conditioned for 22 days at elevated temperatures in a once-through helium loop with 4 ppmv H2O and tested subsequently at elevated temperatures with a pin-on-disk tribometer in an air environment - 650 °C and 750 °C for 800HT; 850 °C and 900 °C for 617 – with various applied loads - 1 N, 2 N and 5 N. SEM-EDS analysis revealed that conditioning the samples in an oxidizing environment leads to the formation of a mixed Fe/Cr-oxide on alloy 800HT and a Cr-oxide on alloy 617, both increasing the wear resistance compared to that of as-received samples. Alloy 617 exhibited lower steady-state friction coefficients compared to those of alloy 800HT. There was a significant decrease in the scatter of the steady-state friction coefficient of the conditioned samples compared to that of the unconditioned samples. The steady-state friction coefficient for alloy 800HT and 617 were found to be 0.53 ± 0.07 and 0.25 ± 0.04, respectively. The wear resistance of alloy 800HT is approximately one order of magnitude lower than that of alloy 617 in all cases that exhibited measurable wear. After sample conditioning, the wear volumes measured at low loads were undistinguishable from the unworn background, a result attributed to the formation of a compacted glaze layer under high temperatures and high contact stresses.
•Friction and wear for alloy 617 are lower than those for alloy 800HT•Conditioning the alloys in impure helium and in air leads to surface oxidation.•Oxidation increases the wear resistance of both alloys.•The formation of a compacted oxide layer glaze results in negligible wear. |
doi_str_mv | 10.1016/j.jnucmat.2019.05.025 |
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•Friction and wear for alloy 617 are lower than those for alloy 800HT•Conditioning the alloys in impure helium and in air leads to surface oxidation.•Oxidation increases the wear resistance of both alloys.•The formation of a compacted oxide layer glaze results in negligible wear.</description><identifier>ISSN: 0022-3115</identifier><identifier>EISSN: 1873-4820</identifier><identifier>DOI: 10.1016/j.jnucmat.2019.05.025</identifier><language>eng</language><publisher>Amsterdam: Elsevier B.V</publisher><subject>Air conditioners ; Alloys ; Alloys 800 and 617 ; Chromium base alloys ; Coefficient of friction ; Contact stresses ; Control rods ; Corrosion ; Environments ; Ferrous alloys ; Friction ; Heat resistant alloys ; Helium ; High temperature ; High temperature gas cooled reactors ; High temperature gases ; HTGR ; Impurities ; Nickel base alloys ; Oxidation ; Reactors ; Sliding contact ; Steady state ; Superalloys ; Temperature ; Temperature effects ; Tribology ; Wear ; Wear resistance</subject><ispartof>Journal of nuclear materials, 2019-08, Vol.522, p.311-323</ispartof><rights>2019 Elsevier B.V.</rights><rights>Copyright Elsevier BV Aug 15, 2019</rights><lds50>peer_reviewed</lds50><oa>free_for_read</oa><woscitedreferencessubscribed>false</woscitedreferencessubscribed><citedby>FETCH-LOGICAL-c411t-562594de791725e93e94fc91341c8dd5dd48aca1323a435f98ee28ef218b7b223</citedby><cites>FETCH-LOGICAL-c411t-562594de791725e93e94fc91341c8dd5dd48aca1323a435f98ee28ef218b7b223</cites></display><links><openurl>$$Topenurl_article</openurl><openurlfulltext>$$Topenurlfull_article</openurlfulltext><thumbnail>$$Tsyndetics_thumb_exl</thumbnail><link.rule.ids>314,780,784,27924,27925</link.rule.ids></links><search><creatorcontrib>Pauly, Valentin</creatorcontrib><creatorcontrib>Tesch, Carter</creatorcontrib><creatorcontrib>Kern, Joseph</creatorcontrib><creatorcontrib>Clark, Malcolm</creatorcontrib><creatorcontrib>Grierson, David</creatorcontrib><creatorcontrib>Singh, Dileep</creatorcontrib><creatorcontrib>Ajayi, Oyelayo</creatorcontrib><creatorcontrib>Sridharan, Kumar</creatorcontrib><title>High-temperature tribological behavior of structural materials after conditioning in impure-helium environments for high-temperature gas-cooled reactor applications</title><title>Journal of nuclear materials</title><description>Incoloy 800HT and Inconel 617 have been selected as candidate structural alloys for the high-temperature gas-cooled reactor (HTGR) concept. Helium, the primary coolant, contains impurities (e.g., H2O and CH4) that can induce corrosion reactions at high temperatures, which in turn can affect the tribological behavior of components in sliding contact such as valves and control-rod drive systems. This paper presents results from the study of the tribological behavior of both alloys before and after conditioning them in either an impure-helium oxidizing environment or in an air environment. Both alloys were conditioned for 22 days at elevated temperatures in a once-through helium loop with 4 ppmv H2O and tested subsequently at elevated temperatures with a pin-on-disk tribometer in an air environment - 650 °C and 750 °C for 800HT; 850 °C and 900 °C for 617 – with various applied loads - 1 N, 2 N and 5 N. SEM-EDS analysis revealed that conditioning the samples in an oxidizing environment leads to the formation of a mixed Fe/Cr-oxide on alloy 800HT and a Cr-oxide on alloy 617, both increasing the wear resistance compared to that of as-received samples. Alloy 617 exhibited lower steady-state friction coefficients compared to those of alloy 800HT. There was a significant decrease in the scatter of the steady-state friction coefficient of the conditioned samples compared to that of the unconditioned samples. The steady-state friction coefficient for alloy 800HT and 617 were found to be 0.53 ± 0.07 and 0.25 ± 0.04, respectively. The wear resistance of alloy 800HT is approximately one order of magnitude lower than that of alloy 617 in all cases that exhibited measurable wear. After sample conditioning, the wear volumes measured at low loads were undistinguishable from the unworn background, a result attributed to the formation of a compacted glaze layer under high temperatures and high contact stresses.
•Friction and wear for alloy 617 are lower than those for alloy 800HT•Conditioning the alloys in impure helium and in air leads to surface oxidation.•Oxidation increases the wear resistance of both alloys.•The formation of a compacted oxide layer glaze results in negligible wear.</description><subject>Air conditioners</subject><subject>Alloys</subject><subject>Alloys 800 and 617</subject><subject>Chromium base alloys</subject><subject>Coefficient of friction</subject><subject>Contact stresses</subject><subject>Control rods</subject><subject>Corrosion</subject><subject>Environments</subject><subject>Ferrous alloys</subject><subject>Friction</subject><subject>Heat resistant alloys</subject><subject>Helium</subject><subject>High temperature</subject><subject>High temperature gas cooled reactors</subject><subject>High temperature gases</subject><subject>HTGR</subject><subject>Impurities</subject><subject>Nickel base alloys</subject><subject>Oxidation</subject><subject>Reactors</subject><subject>Sliding contact</subject><subject>Steady state</subject><subject>Superalloys</subject><subject>Temperature</subject><subject>Temperature effects</subject><subject>Tribology</subject><subject>Wear</subject><subject>Wear resistance</subject><issn>0022-3115</issn><issn>1873-4820</issn><fulltext>true</fulltext><rsrctype>article</rsrctype><creationdate>2019</creationdate><recordtype>article</recordtype><recordid>eNqFkc9q3DAQxkVpodtNH6Eg6NmO_lhZ61RCaJNCIJfkLLTSeHeMLbmSvJD36YNWy-aUS08zDN_8vhk-Qr5x1nLGb67Hdgyrm21pBeO6ZaplQn0gG97vZNP1gn0kG8aEaCTn6jP5kvPIGFOaqQ35-4CHY1NgXiDZsiagJeE-TvGAzk50D0d7wphoHGguaXVVUsfVCxLaKVM71I66GDwWjAHDgWKgOC8V1RxhwnWmEE6YYpghlEyHCju-9zzY3LgYJ_A0gXWlauyyTPWEMzRfkU9DNYOvb3VLXn79fL57aB6f7n_f3T42ruO8NOpGKN152Gm-Ewq0BN0NTnPZcdd7r7zveussl0LaTqpB9wCih0Hwfr_bCyG35PuFu6T4Z4VczBjXFKqlEUJJzWRfaVuiLiqXYs4JBrMknG16NZyZcyBmNG-BmHMghilTA6l7Py57UF84ISSTHUJw4DGBK8ZH_A_hH9nlnG0</recordid><startdate>20190815</startdate><enddate>20190815</enddate><creator>Pauly, Valentin</creator><creator>Tesch, Carter</creator><creator>Kern, Joseph</creator><creator>Clark, Malcolm</creator><creator>Grierson, David</creator><creator>Singh, Dileep</creator><creator>Ajayi, Oyelayo</creator><creator>Sridharan, Kumar</creator><general>Elsevier B.V</general><general>Elsevier BV</general><scope>AAYXX</scope><scope>CITATION</scope><scope>7QQ</scope><scope>7SR</scope><scope>7ST</scope><scope>7TB</scope><scope>7U5</scope><scope>8BQ</scope><scope>8FD</scope><scope>C1K</scope><scope>FR3</scope><scope>JG9</scope><scope>L7M</scope><scope>SOI</scope></search><sort><creationdate>20190815</creationdate><title>High-temperature tribological behavior of structural materials after conditioning in impure-helium environments for high-temperature gas-cooled reactor applications</title><author>Pauly, Valentin ; Tesch, Carter ; Kern, Joseph ; Clark, Malcolm ; Grierson, David ; Singh, Dileep ; Ajayi, Oyelayo ; Sridharan, Kumar</author></sort><facets><frbrtype>5</frbrtype><frbrgroupid>cdi_FETCH-LOGICAL-c411t-562594de791725e93e94fc91341c8dd5dd48aca1323a435f98ee28ef218b7b223</frbrgroupid><rsrctype>articles</rsrctype><prefilter>articles</prefilter><language>eng</language><creationdate>2019</creationdate><topic>Air conditioners</topic><topic>Alloys</topic><topic>Alloys 800 and 617</topic><topic>Chromium base alloys</topic><topic>Coefficient of friction</topic><topic>Contact stresses</topic><topic>Control rods</topic><topic>Corrosion</topic><topic>Environments</topic><topic>Ferrous alloys</topic><topic>Friction</topic><topic>Heat resistant alloys</topic><topic>Helium</topic><topic>High temperature</topic><topic>High temperature gas cooled reactors</topic><topic>High temperature gases</topic><topic>HTGR</topic><topic>Impurities</topic><topic>Nickel base alloys</topic><topic>Oxidation</topic><topic>Reactors</topic><topic>Sliding contact</topic><topic>Steady state</topic><topic>Superalloys</topic><topic>Temperature</topic><topic>Temperature effects</topic><topic>Tribology</topic><topic>Wear</topic><topic>Wear resistance</topic><toplevel>peer_reviewed</toplevel><toplevel>online_resources</toplevel><creatorcontrib>Pauly, Valentin</creatorcontrib><creatorcontrib>Tesch, Carter</creatorcontrib><creatorcontrib>Kern, Joseph</creatorcontrib><creatorcontrib>Clark, Malcolm</creatorcontrib><creatorcontrib>Grierson, David</creatorcontrib><creatorcontrib>Singh, Dileep</creatorcontrib><creatorcontrib>Ajayi, Oyelayo</creatorcontrib><creatorcontrib>Sridharan, Kumar</creatorcontrib><collection>CrossRef</collection><collection>Ceramic Abstracts</collection><collection>Engineered Materials Abstracts</collection><collection>Environment Abstracts</collection><collection>Mechanical & Transportation Engineering Abstracts</collection><collection>Solid State and Superconductivity Abstracts</collection><collection>METADEX</collection><collection>Technology Research Database</collection><collection>Environmental Sciences and Pollution Management</collection><collection>Engineering Research Database</collection><collection>Materials Research Database</collection><collection>Advanced Technologies Database with Aerospace</collection><collection>Environment Abstracts</collection><jtitle>Journal of nuclear materials</jtitle></facets><delivery><delcategory>Remote Search Resource</delcategory><fulltext>fulltext</fulltext></delivery><addata><au>Pauly, Valentin</au><au>Tesch, Carter</au><au>Kern, Joseph</au><au>Clark, Malcolm</au><au>Grierson, David</au><au>Singh, Dileep</au><au>Ajayi, Oyelayo</au><au>Sridharan, Kumar</au><format>journal</format><genre>article</genre><ristype>JOUR</ristype><atitle>High-temperature tribological behavior of structural materials after conditioning in impure-helium environments for high-temperature gas-cooled reactor applications</atitle><jtitle>Journal of nuclear materials</jtitle><date>2019-08-15</date><risdate>2019</risdate><volume>522</volume><spage>311</spage><epage>323</epage><pages>311-323</pages><issn>0022-3115</issn><eissn>1873-4820</eissn><abstract>Incoloy 800HT and Inconel 617 have been selected as candidate structural alloys for the high-temperature gas-cooled reactor (HTGR) concept. Helium, the primary coolant, contains impurities (e.g., H2O and CH4) that can induce corrosion reactions at high temperatures, which in turn can affect the tribological behavior of components in sliding contact such as valves and control-rod drive systems. This paper presents results from the study of the tribological behavior of both alloys before and after conditioning them in either an impure-helium oxidizing environment or in an air environment. Both alloys were conditioned for 22 days at elevated temperatures in a once-through helium loop with 4 ppmv H2O and tested subsequently at elevated temperatures with a pin-on-disk tribometer in an air environment - 650 °C and 750 °C for 800HT; 850 °C and 900 °C for 617 – with various applied loads - 1 N, 2 N and 5 N. SEM-EDS analysis revealed that conditioning the samples in an oxidizing environment leads to the formation of a mixed Fe/Cr-oxide on alloy 800HT and a Cr-oxide on alloy 617, both increasing the wear resistance compared to that of as-received samples. Alloy 617 exhibited lower steady-state friction coefficients compared to those of alloy 800HT. There was a significant decrease in the scatter of the steady-state friction coefficient of the conditioned samples compared to that of the unconditioned samples. The steady-state friction coefficient for alloy 800HT and 617 were found to be 0.53 ± 0.07 and 0.25 ± 0.04, respectively. The wear resistance of alloy 800HT is approximately one order of magnitude lower than that of alloy 617 in all cases that exhibited measurable wear. After sample conditioning, the wear volumes measured at low loads were undistinguishable from the unworn background, a result attributed to the formation of a compacted glaze layer under high temperatures and high contact stresses.
•Friction and wear for alloy 617 are lower than those for alloy 800HT•Conditioning the alloys in impure helium and in air leads to surface oxidation.•Oxidation increases the wear resistance of both alloys.•The formation of a compacted oxide layer glaze results in negligible wear.</abstract><cop>Amsterdam</cop><pub>Elsevier B.V</pub><doi>10.1016/j.jnucmat.2019.05.025</doi><tpages>13</tpages><oa>free_for_read</oa></addata></record> |
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subjects | Air conditioners Alloys Alloys 800 and 617 Chromium base alloys Coefficient of friction Contact stresses Control rods Corrosion Environments Ferrous alloys Friction Heat resistant alloys Helium High temperature High temperature gas cooled reactors High temperature gases HTGR Impurities Nickel base alloys Oxidation Reactors Sliding contact Steady state Superalloys Temperature Temperature effects Tribology Wear Wear resistance |
title | High-temperature tribological behavior of structural materials after conditioning in impure-helium environments for high-temperature gas-cooled reactor applications |
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