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Effect of Impact Block Shape and Material on Impact Wear Behavior of Zr-4 Alloy Cladding Tube
In a pressurized water reactor nuclear power plant, metal foreign matter in the rod–rod gap of the fuel assembly is constantly rubbed and collided with the fuel rod under continuous scouring of the coolant, resulting in wear to the fuel rod and even leakage of the perforation. In this work, the effe...
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Published in: | Metals (Basel ) 2022-10, Vol.12 (10), p.1561 |
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description | In a pressurized water reactor nuclear power plant, metal foreign matter in the rod–rod gap of the fuel assembly is constantly rubbed and collided with the fuel rod under continuous scouring of the coolant, resulting in wear to the fuel rod and even leakage of the perforation. In this work, the effects of different debris shapes and materials on the impact wear behavior of Zr−4 alloy tubes were studied through the dynamic response and damage of Zr−4 alloy tubes under cyclic impact. The results show that the sharper the shape of the impact block, the higher the wear rate of the Zr−4 alloy tube. Although the energy absorption rate of SA 508−A during the impact process is high, most of the energy is used for the wear of the impact block itself and the formation and peeling of the wear debris accumulation layer, and the damage to the Zr−4 alloy tube is small. The wear debris generated by the Zr−4 impact block is not easy to oxidize, and the wear caused by the cyclic impact is more serious. After the Zr−4 impact block cyclically impacts the Zr−4 alloy tube 200 w times, the Zr−4 alloy tube will be perforated due to wear. The oxidation and accumulation of wear debris and the wear mechanism in the impact process are mainly abrasive wear and surface peeling behavior. The occurrence of cutting and wear removal will promote the wear and thinning of the tube wall of the Zr−4 alloy tube, and the tube wall is easily perforated after thinning. |
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In this work, the effects of different debris shapes and materials on the impact wear behavior of Zr−4 alloy tubes were studied through the dynamic response and damage of Zr−4 alloy tubes under cyclic impact. The results show that the sharper the shape of the impact block, the higher the wear rate of the Zr−4 alloy tube. Although the energy absorption rate of SA 508−A during the impact process is high, most of the energy is used for the wear of the impact block itself and the formation and peeling of the wear debris accumulation layer, and the damage to the Zr−4 alloy tube is small. The wear debris generated by the Zr−4 impact block is not easy to oxidize, and the wear caused by the cyclic impact is more serious. After the Zr−4 impact block cyclically impacts the Zr−4 alloy tube 200 w times, the Zr−4 alloy tube will be perforated due to wear. The oxidation and accumulation of wear debris and the wear mechanism in the impact process are mainly abrasive wear and surface peeling behavior. The occurrence of cutting and wear removal will promote the wear and thinning of the tube wall of the Zr−4 alloy tube, and the tube wall is easily perforated after thinning.</description><identifier>ISSN: 2075-4701</identifier><identifier>EISSN: 2075-4701</identifier><identifier>DOI: 10.3390/met12101561</identifier><language>eng</language><publisher>Basel: MDPI AG</publisher><subject>Abrasive cutting ; Abrasive wear ; Accident investigations ; Alloys ; cladding tube ; Cooling ; Corrosion resistance ; Crack initiation ; Cutting wear ; Damage accumulation ; Debris ; Dynamic response ; Energy ; Energy absorption ; Failure ; impact block ; Impact damage ; Impact tests ; Impact wear ; impact wear mechanism ; Morphology ; Nuclear energy ; Nuclear fuel elements ; Nuclear power plants ; Nuclear reactors ; Oxidation ; Peeling ; Perforation ; Pressure vessels ; Pressurized water reactors ; Shape effects ; Specialty metals industry ; Stainless steel ; Thinning ; Tubes ; Velocity ; Wear mechanisms ; Wear particles ; Wear rate ; Zirconium alloys ; Zirconium base alloys ; Zr-4 alloy</subject><ispartof>Metals (Basel ), 2022-10, Vol.12 (10), p.1561</ispartof><rights>COPYRIGHT 2022 MDPI AG</rights><rights>2022 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><citedby>FETCH-LOGICAL-c403t-d07ee06b6263f97b78e279f095f956380900de42396bc88bb997d5c67b01da773</citedby><cites>FETCH-LOGICAL-c403t-d07ee06b6263f97b78e279f095f956380900de42396bc88bb997d5c67b01da773</cites></display><links><openurl>$$Topenurl_article</openurl><openurlfulltext>$$Topenurlfull_article</openurlfulltext><thumbnail>$$Tsyndetics_thumb_exl</thumbnail><linktopdf>$$Uhttps://www.proquest.com/docview/2728510880/fulltextPDF?pq-origsite=primo$$EPDF$$P50$$Gproquest$$Hfree_for_read</linktopdf><linktohtml>$$Uhttps://www.proquest.com/docview/2728510880?pq-origsite=primo$$EHTML$$P50$$Gproquest$$Hfree_for_read</linktohtml><link.rule.ids>314,780,784,25753,27924,27925,37012,44590,75126</link.rule.ids></links><search><creatorcontrib>Yu, Shijia</creatorcontrib><creatorcontrib>Hu, Yong</creatorcontrib><creatorcontrib>Liu, Xin</creatorcontrib><creatorcontrib>Li, Dongxing</creatorcontrib><creatorcontrib>He, Liping</creatorcontrib><creatorcontrib>Wang, Jun</creatorcontrib><creatorcontrib>Cai, Zhenbing</creatorcontrib><title>Effect of Impact Block Shape and Material on Impact Wear Behavior of Zr-4 Alloy Cladding Tube</title><title>Metals (Basel )</title><description>In a pressurized water reactor nuclear power plant, metal foreign matter in the rod–rod gap of the fuel assembly is constantly rubbed and collided with the fuel rod under continuous scouring of the coolant, resulting in wear to the fuel rod and even leakage of the perforation. In this work, the effects of different debris shapes and materials on the impact wear behavior of Zr−4 alloy tubes were studied through the dynamic response and damage of Zr−4 alloy tubes under cyclic impact. The results show that the sharper the shape of the impact block, the higher the wear rate of the Zr−4 alloy tube. Although the energy absorption rate of SA 508−A during the impact process is high, most of the energy is used for the wear of the impact block itself and the formation and peeling of the wear debris accumulation layer, and the damage to the Zr−4 alloy tube is small. The wear debris generated by the Zr−4 impact block is not easy to oxidize, and the wear caused by the cyclic impact is more serious. After the Zr−4 impact block cyclically impacts the Zr−4 alloy tube 200 w times, the Zr−4 alloy tube will be perforated due to wear. The oxidation and accumulation of wear debris and the wear mechanism in the impact process are mainly abrasive wear and surface peeling behavior. The occurrence of cutting and wear removal will promote the wear and thinning of the tube wall of the Zr−4 alloy tube, and the tube wall is easily perforated after thinning.</description><subject>Abrasive cutting</subject><subject>Abrasive wear</subject><subject>Accident investigations</subject><subject>Alloys</subject><subject>cladding tube</subject><subject>Cooling</subject><subject>Corrosion resistance</subject><subject>Crack initiation</subject><subject>Cutting wear</subject><subject>Damage accumulation</subject><subject>Debris</subject><subject>Dynamic response</subject><subject>Energy</subject><subject>Energy absorption</subject><subject>Failure</subject><subject>impact block</subject><subject>Impact damage</subject><subject>Impact tests</subject><subject>Impact wear</subject><subject>impact wear mechanism</subject><subject>Morphology</subject><subject>Nuclear energy</subject><subject>Nuclear fuel elements</subject><subject>Nuclear power plants</subject><subject>Nuclear reactors</subject><subject>Oxidation</subject><subject>Peeling</subject><subject>Perforation</subject><subject>Pressure vessels</subject><subject>Pressurized water reactors</subject><subject>Shape effects</subject><subject>Specialty metals industry</subject><subject>Stainless steel</subject><subject>Thinning</subject><subject>Tubes</subject><subject>Velocity</subject><subject>Wear mechanisms</subject><subject>Wear particles</subject><subject>Wear rate</subject><subject>Zirconium alloys</subject><subject>Zirconium base alloys</subject><subject>Zr-4 alloy</subject><issn>2075-4701</issn><issn>2075-4701</issn><fulltext>true</fulltext><rsrctype>article</rsrctype><creationdate>2022</creationdate><recordtype>article</recordtype><sourceid>PIMPY</sourceid><sourceid>DOA</sourceid><recordid>eNpNUU1rFEEQHUTBEHPyDzR4lInV3dNfx80S40LEgxFBkKY_qje9zk6vPbNC_r0dVyVVhyoe7z1eUV33msIl5wbe7XGhjAIVkj7rzhgo0Q8K6PMn-8vuYp530EozCcacdd-vU8KwkJLIZn9wbbsaS_hBPt-7AxI3RfLRLVizG0mZ_lG-oqvkCu_dr1zqo_Rb7QeyGsfyQNajizFPW3J39Piqe5HcOOPF33nefXl_fbf-0N9-utmsV7d9GIAvfQSFCNJLJnkyyiuNTJkERiQjJNdgACIOjBvpg9beG6OiCFJ5oNEpxc-7zck3Frezh5r3rj7Y4rL9A5S6ta4uOYxoB5Y4CG-8C2rggWmvhTJB6QYGiax5vTl5HWr5ecR5sbtyrFOLb5liWlDQGhrr8sTaumaap1SW6kLriPscyoQpN3ylBqF1u5E3wduTINQyzxXT_5gU7OP_7JP_8d_6H4lJ</recordid><startdate>20221001</startdate><enddate>20221001</enddate><creator>Yu, Shijia</creator><creator>Hu, Yong</creator><creator>Liu, Xin</creator><creator>Li, Dongxing</creator><creator>He, Liping</creator><creator>Wang, Jun</creator><creator>Cai, Zhenbing</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>PRINS</scope><scope>DOA</scope></search><sort><creationdate>20221001</creationdate><title>Effect of Impact Block Shape and Material on Impact Wear Behavior of Zr-4 Alloy Cladding Tube</title><author>Yu, Shijia ; Hu, Yong ; Liu, Xin ; Li, Dongxing ; He, Liping ; Wang, Jun ; Cai, Zhenbing</author></sort><facets><frbrtype>5</frbrtype><frbrgroupid>cdi_FETCH-LOGICAL-c403t-d07ee06b6263f97b78e279f095f956380900de42396bc88bb997d5c67b01da773</frbrgroupid><rsrctype>articles</rsrctype><prefilter>articles</prefilter><language>eng</language><creationdate>2022</creationdate><topic>Abrasive cutting</topic><topic>Abrasive wear</topic><topic>Accident investigations</topic><topic>Alloys</topic><topic>cladding tube</topic><topic>Cooling</topic><topic>Corrosion resistance</topic><topic>Crack initiation</topic><topic>Cutting wear</topic><topic>Damage accumulation</topic><topic>Debris</topic><topic>Dynamic response</topic><topic>Energy</topic><topic>Energy absorption</topic><topic>Failure</topic><topic>impact block</topic><topic>Impact damage</topic><topic>Impact tests</topic><topic>Impact wear</topic><topic>impact wear mechanism</topic><topic>Morphology</topic><topic>Nuclear energy</topic><topic>Nuclear fuel elements</topic><topic>Nuclear power plants</topic><topic>Nuclear reactors</topic><topic>Oxidation</topic><topic>Peeling</topic><topic>Perforation</topic><topic>Pressure vessels</topic><topic>Pressurized water reactors</topic><topic>Shape effects</topic><topic>Specialty metals industry</topic><topic>Stainless steel</topic><topic>Thinning</topic><topic>Tubes</topic><topic>Velocity</topic><topic>Wear mechanisms</topic><topic>Wear particles</topic><topic>Wear rate</topic><topic>Zirconium alloys</topic><topic>Zirconium base alloys</topic><topic>Zr-4 alloy</topic><toplevel>peer_reviewed</toplevel><toplevel>online_resources</toplevel><creatorcontrib>Yu, Shijia</creatorcontrib><creatorcontrib>Hu, Yong</creatorcontrib><creatorcontrib>Liu, Xin</creatorcontrib><creatorcontrib>Li, Dongxing</creatorcontrib><creatorcontrib>He, Liping</creatorcontrib><creatorcontrib>Wang, Jun</creatorcontrib><creatorcontrib>Cai, Zhenbing</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 UK/Ireland</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</collection><collection>Materials Research Database</collection><collection>Materials Science Database</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>ProQuest Central China</collection><collection>DOAJ Directory of Open Access Journals</collection><jtitle>Metals (Basel )</jtitle></facets><delivery><delcategory>Remote Search Resource</delcategory><fulltext>fulltext</fulltext></delivery><addata><au>Yu, Shijia</au><au>Hu, Yong</au><au>Liu, Xin</au><au>Li, Dongxing</au><au>He, Liping</au><au>Wang, Jun</au><au>Cai, Zhenbing</au><format>journal</format><genre>article</genre><ristype>JOUR</ristype><atitle>Effect of Impact Block Shape and Material on Impact Wear Behavior of Zr-4 Alloy Cladding Tube</atitle><jtitle>Metals (Basel )</jtitle><date>2022-10-01</date><risdate>2022</risdate><volume>12</volume><issue>10</issue><spage>1561</spage><pages>1561-</pages><issn>2075-4701</issn><eissn>2075-4701</eissn><abstract>In a pressurized water reactor nuclear power plant, metal foreign matter in the rod–rod gap of the fuel assembly is constantly rubbed and collided with the fuel rod under continuous scouring of the coolant, resulting in wear to the fuel rod and even leakage of the perforation. In this work, the effects of different debris shapes and materials on the impact wear behavior of Zr−4 alloy tubes were studied through the dynamic response and damage of Zr−4 alloy tubes under cyclic impact. The results show that the sharper the shape of the impact block, the higher the wear rate of the Zr−4 alloy tube. Although the energy absorption rate of SA 508−A during the impact process is high, most of the energy is used for the wear of the impact block itself and the formation and peeling of the wear debris accumulation layer, and the damage to the Zr−4 alloy tube is small. The wear debris generated by the Zr−4 impact block is not easy to oxidize, and the wear caused by the cyclic impact is more serious. After the Zr−4 impact block cyclically impacts the Zr−4 alloy tube 200 w times, the Zr−4 alloy tube will be perforated due to wear. The oxidation and accumulation of wear debris and the wear mechanism in the impact process are mainly abrasive wear and surface peeling behavior. The occurrence of cutting and wear removal will promote the wear and thinning of the tube wall of the Zr−4 alloy tube, and the tube wall is easily perforated after thinning.</abstract><cop>Basel</cop><pub>MDPI AG</pub><doi>10.3390/met12101561</doi><oa>free_for_read</oa></addata></record> |
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subjects | Abrasive cutting Abrasive wear Accident investigations Alloys cladding tube Cooling Corrosion resistance Crack initiation Cutting wear Damage accumulation Debris Dynamic response Energy Energy absorption Failure impact block Impact damage Impact tests Impact wear impact wear mechanism Morphology Nuclear energy Nuclear fuel elements Nuclear power plants Nuclear reactors Oxidation Peeling Perforation Pressure vessels Pressurized water reactors Shape effects Specialty metals industry Stainless steel Thinning Tubes Velocity Wear mechanisms Wear particles Wear rate Zirconium alloys Zirconium base alloys Zr-4 alloy |
title | Effect of Impact Block Shape and Material on Impact Wear Behavior of Zr-4 Alloy Cladding Tube |
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