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A Study on the Aging Behavior of Nitrided W18Cr4V Steel in High-Temperature Sodium
The loading and unloading elevators are the primary equipment in the refueling system, used for transferring fuel assemblies in the sodium-cooled fast reactors. The guideway friction pairs are the critical components of these elevators in the refueling system. With the excellent hardness and wear re...
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Published in: | Metals (Basel ) 2024-03, Vol.14 (3), p.357 |
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description | The loading and unloading elevators are the primary equipment in the refueling system, used for transferring fuel assemblies in the sodium-cooled fast reactors. The guideway friction pairs are the critical components of these elevators in the refueling system. With the excellent hardness and wear resistance in air, nitrided W18Cr4V steel is a promising material for the guideway friction pairs. In order to assess the feasibility of using nitrided W18Cr4V steel, it is essential to understand the aging behavior of nitrided W18Cr4V steel in high-temperature sodium. Aging tests were conducted on nitrided W18Cr4V steel in sodium and in argon environments at various temperatures for different exposure times. The results showed that the nitrogen atoms in the nitrided layer exhibited bidirectional diffusion behavior in the sodium or argon environment at 540 °C. Compared to the argon environment, cracks formed within the nitrided layer and the diffusion of nitrogen into the sodium was accelerated in the nitrided layer. As a significant number of nitrogen atoms had diffused into the sodium, there was little difference in the hardness between nitrided W18Cr4V steel and non-nitrided W18Cr4V steel after long-term exposure to 540 °C sodium. |
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The guideway friction pairs are the critical components of these elevators in the refueling system. With the excellent hardness and wear resistance in air, nitrided W18Cr4V steel is a promising material for the guideway friction pairs. In order to assess the feasibility of using nitrided W18Cr4V steel, it is essential to understand the aging behavior of nitrided W18Cr4V steel in high-temperature sodium. Aging tests were conducted on nitrided W18Cr4V steel in sodium and in argon environments at various temperatures for different exposure times. The results showed that the nitrogen atoms in the nitrided layer exhibited bidirectional diffusion behavior in the sodium or argon environment at 540 °C. Compared to the argon environment, cracks formed within the nitrided layer and the diffusion of nitrogen into the sodium was accelerated in the nitrided layer. As a significant number of nitrogen atoms had diffused into the sodium, there was little difference in the hardness between nitrided W18Cr4V steel and non-nitrided W18Cr4V steel after long-term exposure to 540 °C sodium.</description><identifier>ISSN: 2075-4701</identifier><identifier>EISSN: 2075-4701</identifier><identifier>DOI: 10.3390/met14030357</identifier><language>eng</language><publisher>Basel: MDPI AG</publisher><subject>Aging ; Aging (metallurgy) ; aging behavior ; Alcohol ; Argon ; Atomic properties ; Critical components ; Diffusion layers ; Elevators & escalators ; fast reactor ; Friction ; Guideways ; Hardness ; Heat resistance ; Heat resistant steels ; High temperature ; high-temperature sodium ; Manufacturing ; nitrided W18Cr4V steel ; Nitriding ; Nitrogen ; Nitrogen atoms ; Nuclear energy ; Nuclear reactors ; Reactors ; Refueling ; Sodium ; Sodium cooled reactors ; Steel ; Temperature ; Wear resistance</subject><ispartof>Metals (Basel ), 2024-03, Vol.14 (3), p.357</ispartof><rights>COPYRIGHT 2024 MDPI AG</rights><rights>2024 by the authors. Licensee MDPI, Basel, Switzerland. This article is an open access article distributed under the terms and conditions of the Creative Commons Attribution (CC BY) license (https://creativecommons.org/licenses/by/4.0/). Notwithstanding the ProQuest Terms and Conditions, you may use this content in accordance with the terms of the License.</rights><lds50>peer_reviewed</lds50><oa>free_for_read</oa><woscitedreferencessubscribed>false</woscitedreferencessubscribed><cites>FETCH-LOGICAL-c361t-8caf9e789854c4c7616fe7def15d7d03f6654e664c1223d69ff5cad01db8a3eb3</cites><orcidid>0000-0002-1489-4792</orcidid></display><links><openurl>$$Topenurl_article</openurl><openurlfulltext>$$Topenurlfull_article</openurlfulltext><thumbnail>$$Tsyndetics_thumb_exl</thumbnail><linktopdf>$$Uhttps://www.proquest.com/docview/3003354758/fulltextPDF?pq-origsite=primo$$EPDF$$P50$$Gproquest$$Hfree_for_read</linktopdf><linktohtml>$$Uhttps://www.proquest.com/docview/3003354758?pq-origsite=primo$$EHTML$$P50$$Gproquest$$Hfree_for_read</linktohtml><link.rule.ids>314,777,781,25734,27905,27906,36993,44571,74875</link.rule.ids></links><search><creatorcontrib>Fu, Xiaogang</creatorcontrib><creatorcontrib>Liang, Na</creatorcontrib><creatorcontrib>Zhang, Wei</creatorcontrib><creatorcontrib>Tao, Liu</creatorcontrib><creatorcontrib>Qin, Bo</creatorcontrib><creatorcontrib>Ruan, Zhangshun</creatorcontrib><creatorcontrib>Long, Bin</creatorcontrib><creatorcontrib>Lv, Shasha</creatorcontrib><title>A Study on the Aging Behavior of Nitrided W18Cr4V Steel in High-Temperature Sodium</title><title>Metals (Basel )</title><description>The loading and unloading elevators are the primary equipment in the refueling system, used for transferring fuel assemblies in the sodium-cooled fast reactors. The guideway friction pairs are the critical components of these elevators in the refueling system. With the excellent hardness and wear resistance in air, nitrided W18Cr4V steel is a promising material for the guideway friction pairs. In order to assess the feasibility of using nitrided W18Cr4V steel, it is essential to understand the aging behavior of nitrided W18Cr4V steel in high-temperature sodium. Aging tests were conducted on nitrided W18Cr4V steel in sodium and in argon environments at various temperatures for different exposure times. The results showed that the nitrogen atoms in the nitrided layer exhibited bidirectional diffusion behavior in the sodium or argon environment at 540 °C. Compared to the argon environment, cracks formed within the nitrided layer and the diffusion of nitrogen into the sodium was accelerated in the nitrided layer. As a significant number of nitrogen atoms had diffused into the sodium, there was little difference in the hardness between nitrided W18Cr4V steel and non-nitrided W18Cr4V steel after long-term exposure to 540 °C sodium.</description><subject>Aging</subject><subject>Aging (metallurgy)</subject><subject>aging behavior</subject><subject>Alcohol</subject><subject>Argon</subject><subject>Atomic properties</subject><subject>Critical components</subject><subject>Diffusion layers</subject><subject>Elevators & escalators</subject><subject>fast reactor</subject><subject>Friction</subject><subject>Guideways</subject><subject>Hardness</subject><subject>Heat resistance</subject><subject>Heat resistant steels</subject><subject>High temperature</subject><subject>high-temperature sodium</subject><subject>Manufacturing</subject><subject>nitrided W18Cr4V steel</subject><subject>Nitriding</subject><subject>Nitrogen</subject><subject>Nitrogen atoms</subject><subject>Nuclear energy</subject><subject>Nuclear reactors</subject><subject>Reactors</subject><subject>Refueling</subject><subject>Sodium</subject><subject>Sodium cooled reactors</subject><subject>Steel</subject><subject>Temperature</subject><subject>Wear resistance</subject><issn>2075-4701</issn><issn>2075-4701</issn><fulltext>true</fulltext><rsrctype>article</rsrctype><creationdate>2024</creationdate><recordtype>article</recordtype><sourceid>PIMPY</sourceid><sourceid>DOA</sourceid><recordid>eNpNUV1r3DAQNKWBhjRP_QOCPhYnK-vTj9ejbQKhhSZpH4UsrXw6ztZVlgv591V6pWT3YZdhZhh2m-YdhSvGeriesFAODJhQr5rzDpRouQL6-sX-prlclj3U0p2Evj9vvm_IfVn9E0kzKTskmzHOI_mIO_s7pkxSIF9jydGjJz-p3mb-o_IRDyTO5CaOu_YBpyNmW9aM5D75uE5vm7NgDwte_psXzePnTw_bm_bu25fb7eaudUzS0mpnQ49K91pwx52SVAZUHgMVXnlgQUrBUUruaNcxL_sQhLMeqB-0ZTiwi-b25OuT3ZtjjpPNTybZaP4CKY_G5hLdAU1nOSjgA3gJXMnB-hBQcNHzQQV0qnq9P3kdc_q14lLMPq15rvENA2BMcCV0ZV2dWKOtpnEOqWTranucokszhljxjdK6E_W6vAo-nAQup2XJGP7HpGCen2ZePI39AeiSh0E</recordid><startdate>20240301</startdate><enddate>20240301</enddate><creator>Fu, Xiaogang</creator><creator>Liang, Na</creator><creator>Zhang, Wei</creator><creator>Tao, Liu</creator><creator>Qin, Bo</creator><creator>Ruan, Zhangshun</creator><creator>Long, Bin</creator><creator>Lv, Shasha</creator><general>MDPI AG</general><scope>AAYXX</scope><scope>CITATION</scope><scope>8BQ</scope><scope>8FD</scope><scope>8FE</scope><scope>8FG</scope><scope>ABJCF</scope><scope>ABUWG</scope><scope>AFKRA</scope><scope>AZQEC</scope><scope>BENPR</scope><scope>BGLVJ</scope><scope>CCPQU</scope><scope>D1I</scope><scope>DWQXO</scope><scope>HCIFZ</scope><scope>JG9</scope><scope>KB.</scope><scope>PDBOC</scope><scope>PIMPY</scope><scope>PQEST</scope><scope>PQQKQ</scope><scope>PQUKI</scope><scope>DOA</scope><orcidid>https://orcid.org/0000-0002-1489-4792</orcidid></search><sort><creationdate>20240301</creationdate><title>A Study on the Aging Behavior of Nitrided W18Cr4V Steel in High-Temperature Sodium</title><author>Fu, Xiaogang ; Liang, Na ; Zhang, Wei ; Tao, Liu ; Qin, Bo ; Ruan, Zhangshun ; Long, Bin ; Lv, Shasha</author></sort><facets><frbrtype>5</frbrtype><frbrgroupid>cdi_FETCH-LOGICAL-c361t-8caf9e789854c4c7616fe7def15d7d03f6654e664c1223d69ff5cad01db8a3eb3</frbrgroupid><rsrctype>articles</rsrctype><prefilter>articles</prefilter><language>eng</language><creationdate>2024</creationdate><topic>Aging</topic><topic>Aging (metallurgy)</topic><topic>aging behavior</topic><topic>Alcohol</topic><topic>Argon</topic><topic>Atomic properties</topic><topic>Critical components</topic><topic>Diffusion layers</topic><topic>Elevators & escalators</topic><topic>fast reactor</topic><topic>Friction</topic><topic>Guideways</topic><topic>Hardness</topic><topic>Heat resistance</topic><topic>Heat resistant steels</topic><topic>High temperature</topic><topic>high-temperature sodium</topic><topic>Manufacturing</topic><topic>nitrided W18Cr4V steel</topic><topic>Nitriding</topic><topic>Nitrogen</topic><topic>Nitrogen atoms</topic><topic>Nuclear energy</topic><topic>Nuclear reactors</topic><topic>Reactors</topic><topic>Refueling</topic><topic>Sodium</topic><topic>Sodium cooled reactors</topic><topic>Steel</topic><topic>Temperature</topic><topic>Wear resistance</topic><toplevel>peer_reviewed</toplevel><toplevel>online_resources</toplevel><creatorcontrib>Fu, Xiaogang</creatorcontrib><creatorcontrib>Liang, Na</creatorcontrib><creatorcontrib>Zhang, Wei</creatorcontrib><creatorcontrib>Tao, Liu</creatorcontrib><creatorcontrib>Qin, Bo</creatorcontrib><creatorcontrib>Ruan, Zhangshun</creatorcontrib><creatorcontrib>Long, Bin</creatorcontrib><creatorcontrib>Lv, Shasha</creatorcontrib><collection>CrossRef</collection><collection>METADEX</collection><collection>Technology Research Database</collection><collection>ProQuest SciTech Collection</collection><collection>ProQuest Technology Collection</collection><collection>Materials Science & Engineering Collection</collection><collection>ProQuest Central (Alumni)</collection><collection>ProQuest Central</collection><collection>ProQuest Central Essentials</collection><collection>AUTh Library subscriptions: ProQuest Central</collection><collection>Technology Collection</collection><collection>ProQuest One Community College</collection><collection>ProQuest Materials Science Collection</collection><collection>ProQuest Central Korea</collection><collection>SciTech Premium Collection (Proquest) (PQ_SDU_P3)</collection><collection>Materials Research Database</collection><collection>https://resources.nclive.org/materials</collection><collection>Materials science collection</collection><collection>Publicly Available Content Database</collection><collection>ProQuest One Academic Eastern Edition (DO NOT USE)</collection><collection>ProQuest One Academic</collection><collection>ProQuest One Academic UKI Edition</collection><collection>Open Access: DOAJ - Directory of Open Access Journals</collection><jtitle>Metals (Basel )</jtitle></facets><delivery><delcategory>Remote Search Resource</delcategory><fulltext>fulltext</fulltext></delivery><addata><au>Fu, Xiaogang</au><au>Liang, Na</au><au>Zhang, Wei</au><au>Tao, Liu</au><au>Qin, Bo</au><au>Ruan, Zhangshun</au><au>Long, Bin</au><au>Lv, Shasha</au><format>journal</format><genre>article</genre><ristype>JOUR</ristype><atitle>A Study on the Aging Behavior of Nitrided W18Cr4V Steel in High-Temperature Sodium</atitle><jtitle>Metals (Basel )</jtitle><date>2024-03-01</date><risdate>2024</risdate><volume>14</volume><issue>3</issue><spage>357</spage><pages>357-</pages><issn>2075-4701</issn><eissn>2075-4701</eissn><abstract>The loading and unloading elevators are the primary equipment in the refueling system, used for transferring fuel assemblies in the sodium-cooled fast reactors. The guideway friction pairs are the critical components of these elevators in the refueling system. With the excellent hardness and wear resistance in air, nitrided W18Cr4V steel is a promising material for the guideway friction pairs. In order to assess the feasibility of using nitrided W18Cr4V steel, it is essential to understand the aging behavior of nitrided W18Cr4V steel in high-temperature sodium. Aging tests were conducted on nitrided W18Cr4V steel in sodium and in argon environments at various temperatures for different exposure times. The results showed that the nitrogen atoms in the nitrided layer exhibited bidirectional diffusion behavior in the sodium or argon environment at 540 °C. Compared to the argon environment, cracks formed within the nitrided layer and the diffusion of nitrogen into the sodium was accelerated in the nitrided layer. As a significant number of nitrogen atoms had diffused into the sodium, there was little difference in the hardness between nitrided W18Cr4V steel and non-nitrided W18Cr4V steel after long-term exposure to 540 °C sodium.</abstract><cop>Basel</cop><pub>MDPI AG</pub><doi>10.3390/met14030357</doi><orcidid>https://orcid.org/0000-0002-1489-4792</orcidid><oa>free_for_read</oa></addata></record> |
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subjects | Aging Aging (metallurgy) aging behavior Alcohol Argon Atomic properties Critical components Diffusion layers Elevators & escalators fast reactor Friction Guideways Hardness Heat resistance Heat resistant steels High temperature high-temperature sodium Manufacturing nitrided W18Cr4V steel Nitriding Nitrogen Nitrogen atoms Nuclear energy Nuclear reactors Reactors Refueling Sodium Sodium cooled reactors Steel Temperature Wear resistance |
title | A Study on the Aging Behavior of Nitrided W18Cr4V Steel in High-Temperature Sodium |
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