Friction Performance Analysis of Reactor Coolant Pump Shaft Seal Based on Sensor and Computer Simulation
In recent years, the state has put forward a grand plan to develop nuclear power in order to control environmental pollution and carbon emissions. In nuclear power plants, mechanical seals for reactor coolant pump play an important role in nuclear power safety production. However, China cannot indep...
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Veröffentlicht in: | Journal of sensors 2022-09, Vol.2022, p.1-11 |
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description | In recent years, the state has put forward a grand plan to develop nuclear power in order to control environmental pollution and carbon emissions. In nuclear power plants, mechanical seals for reactor coolant pump play an important role in nuclear power safety production. However, China cannot independently produce such mechanical seals, and they are blocked by foreign related technologies, which has seriously affected China’s nuclear power development plan and the overall safety of China’s nuclear power operation. Under this background, this paper studies the friction performance of the shaft seal of the reactor coolant pump, uses the sensor to obtain the data of friction factors such as low-pressure leakage, effectively monitors the low-pressure leakage through calculation and simulation modeling, truly reflects the operating state of the reactor coolant pump, and provides a new research direction and experimental basis for further analysis of the friction performance of the shaft seal of the reactor coolant pump. The results show that under the joint action of the pressure difference and the force generated by the deformation of the moving ring plate, the cone angle formed on the seal end face is 1300.9 μ convergence gap of rad. When the inlet water temperature is 65°C, the leakage rate is 1867.8 L/h. The deformation of the moving ring deformation ring plate can hinder the increase of the deformation cone angle of the moving ring. The greater the thickness of the moving ring deformation ring plate, the greater the seal leakage rate. The inlet temperature of the sealing medium and the friction performance of the material also have an impact on the sealing performance. |
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In nuclear power plants, mechanical seals for reactor coolant pump play an important role in nuclear power safety production. However, China cannot independently produce such mechanical seals, and they are blocked by foreign related technologies, which has seriously affected China’s nuclear power development plan and the overall safety of China’s nuclear power operation. Under this background, this paper studies the friction performance of the shaft seal of the reactor coolant pump, uses the sensor to obtain the data of friction factors such as low-pressure leakage, effectively monitors the low-pressure leakage through calculation and simulation modeling, truly reflects the operating state of the reactor coolant pump, and provides a new research direction and experimental basis for further analysis of the friction performance of the shaft seal of the reactor coolant pump. The results show that under the joint action of the pressure difference and the force generated by the deformation of the moving ring plate, the cone angle formed on the seal end face is 1300.9 μ convergence gap of rad. When the inlet water temperature is 65°C, the leakage rate is 1867.8 L/h. The deformation of the moving ring deformation ring plate can hinder the increase of the deformation cone angle of the moving ring. The greater the thickness of the moving ring deformation ring plate, the greater the seal leakage rate. The inlet temperature of the sealing medium and the friction performance of the material also have an impact on the sealing performance.</description><identifier>ISSN: 1687-725X</identifier><identifier>EISSN: 1687-7268</identifier><identifier>DOI: 10.1155/2022/7838491</identifier><language>eng</language><publisher>New York: Hindawi</publisher><subject>Computer simulation ; Coolant pumps ; Deformation ; Friction ; High temperature ; Inlet temperature ; Leakage ; Localization ; Low pressure ; Lubricants & lubrication ; Nuclear energy ; Nuclear power plants ; Nuclear reactors ; Nuclear safety ; Sealing ; Seals ; Seals (stoppers) ; Sensors ; Water temperature ; Working conditions</subject><ispartof>Journal of sensors, 2022-09, Vol.2022, p.1-11</ispartof><rights>Copyright © 2022 Qiuqin Gou et al.</rights><rights>Copyright © 2022 Qiuqin Gou et al. This is an open access article distributed under the Creative Commons Attribution License (the “License”), which permits unrestricted use, distribution, and reproduction in any medium, provided the original work is properly cited. Notwithstanding the ProQuest Terms and Conditions, you may use this content in accordance with the terms of the License. https://creativecommons.org/licenses/by/4.0</rights><lds50>peer_reviewed</lds50><oa>free_for_read</oa><woscitedreferencessubscribed>false</woscitedreferencessubscribed><citedby>FETCH-LOGICAL-c404t-6f835257553dc459c4524a94e8f835f5cb4f67c238a2328c1e68ed991cae41013</citedby><cites>FETCH-LOGICAL-c404t-6f835257553dc459c4524a94e8f835f5cb4f67c238a2328c1e68ed991cae41013</cites><orcidid>0000-0002-8835-5863</orcidid></display><links><openurl>$$Topenurl_article</openurl><openurlfulltext>$$Topenurlfull_article</openurlfulltext><thumbnail>$$Tsyndetics_thumb_exl</thumbnail><link.rule.ids>314,780,784,27923,27924</link.rule.ids></links><search><contributor>Fan, Yaxiang</contributor><contributor>Yaxiang Fan</contributor><creatorcontrib>Gou, Qiuqin</creatorcontrib><creatorcontrib>Xiao, Shide</creatorcontrib><creatorcontrib>Chen, Xiaoming</creatorcontrib><title>Friction Performance Analysis of Reactor Coolant Pump Shaft Seal Based on Sensor and Computer Simulation</title><title>Journal of sensors</title><description>In recent years, the state has put forward a grand plan to develop nuclear power in order to control environmental pollution and carbon emissions. In nuclear power plants, mechanical seals for reactor coolant pump play an important role in nuclear power safety production. However, China cannot independently produce such mechanical seals, and they are blocked by foreign related technologies, which has seriously affected China’s nuclear power development plan and the overall safety of China’s nuclear power operation. Under this background, this paper studies the friction performance of the shaft seal of the reactor coolant pump, uses the sensor to obtain the data of friction factors such as low-pressure leakage, effectively monitors the low-pressure leakage through calculation and simulation modeling, truly reflects the operating state of the reactor coolant pump, and provides a new research direction and experimental basis for further analysis of the friction performance of the shaft seal of the reactor coolant pump. The results show that under the joint action of the pressure difference and the force generated by the deformation of the moving ring plate, the cone angle formed on the seal end face is 1300.9 μ convergence gap of rad. When the inlet water temperature is 65°C, the leakage rate is 1867.8 L/h. The deformation of the moving ring deformation ring plate can hinder the increase of the deformation cone angle of the moving ring. The greater the thickness of the moving ring deformation ring plate, the greater the seal leakage rate. The inlet temperature of the sealing medium and the friction performance of the material also have an impact on the sealing performance.</description><subject>Computer simulation</subject><subject>Coolant pumps</subject><subject>Deformation</subject><subject>Friction</subject><subject>High temperature</subject><subject>Inlet temperature</subject><subject>Leakage</subject><subject>Localization</subject><subject>Low pressure</subject><subject>Lubricants & lubrication</subject><subject>Nuclear energy</subject><subject>Nuclear power plants</subject><subject>Nuclear reactors</subject><subject>Nuclear safety</subject><subject>Sealing</subject><subject>Seals</subject><subject>Seals (stoppers)</subject><subject>Sensors</subject><subject>Water temperature</subject><subject>Working conditions</subject><issn>1687-725X</issn><issn>1687-7268</issn><fulltext>true</fulltext><rsrctype>article</rsrctype><creationdate>2022</creationdate><recordtype>article</recordtype><sourceid>RHX</sourceid><sourceid>ABUWG</sourceid><sourceid>AFKRA</sourceid><sourceid>AZQEC</sourceid><sourceid>BENPR</sourceid><sourceid>CCPQU</sourceid><sourceid>DWQXO</sourceid><sourceid>GNUQQ</sourceid><recordid>eNp90F1LwzAUBuAgCs7pnT8g4KXW5bNJL-dwKgwcVsG7ckwT1tE2M2mR_XtbNrz0IpzAeXjhvAhdU3JPqZQzRhibKc21yOgJmtBUq0SxVJ_-_eXnObqIcUtIyhXnE7RZhsp0lW_x2gbnQwOtsXjeQr2PVcTe4TcLpvMBL7yvoe3wum92ON-A63BuocYPEG2Jh4DctnFw0JaDbXZ9ZwPOq6avYcy_RGcO6mivjnOKPpaP74vnZPX69LKYrxIjiOiS1GkumVRS8tIImQ2PCciE1ePCSfMlXKoM4xoYZ9pQm2pbZhk1YAUllE_RzSF3F_x3b2NXbH0fhntiwRRVkmpO1KDuDsoEH2OwrtiFqoGwLygpxi6Lscvi2OXAbw98U7Ul_FT_6190Z3Lm</recordid><startdate>20220917</startdate><enddate>20220917</enddate><creator>Gou, Qiuqin</creator><creator>Xiao, Shide</creator><creator>Chen, Xiaoming</creator><general>Hindawi</general><general>Hindawi Limited</general><scope>RHU</scope><scope>RHW</scope><scope>RHX</scope><scope>AAYXX</scope><scope>CITATION</scope><scope>3V.</scope><scope>7SP</scope><scope>7U5</scope><scope>7XB</scope><scope>8AL</scope><scope>8FD</scope><scope>8FE</scope><scope>8FG</scope><scope>8FK</scope><scope>ABJCF</scope><scope>ABUWG</scope><scope>AFKRA</scope><scope>ARAPS</scope><scope>AZQEC</scope><scope>BENPR</scope><scope>BGLVJ</scope><scope>CCPQU</scope><scope>CWDGH</scope><scope>D1I</scope><scope>DWQXO</scope><scope>GNUQQ</scope><scope>HCIFZ</scope><scope>JQ2</scope><scope>K7-</scope><scope>KB.</scope><scope>L6V</scope><scope>L7M</scope><scope>M0N</scope><scope>M7S</scope><scope>P5Z</scope><scope>P62</scope><scope>PDBOC</scope><scope>PIMPY</scope><scope>PQEST</scope><scope>PQQKQ</scope><scope>PQUKI</scope><scope>PRINS</scope><scope>PTHSS</scope><scope>Q9U</scope><orcidid>https://orcid.org/0000-0002-8835-5863</orcidid></search><sort><creationdate>20220917</creationdate><title>Friction Performance Analysis of Reactor Coolant Pump Shaft Seal Based on Sensor and Computer Simulation</title><author>Gou, Qiuqin ; Xiao, Shide ; Chen, Xiaoming</author></sort><facets><frbrtype>5</frbrtype><frbrgroupid>cdi_FETCH-LOGICAL-c404t-6f835257553dc459c4524a94e8f835f5cb4f67c238a2328c1e68ed991cae41013</frbrgroupid><rsrctype>articles</rsrctype><prefilter>articles</prefilter><language>eng</language><creationdate>2022</creationdate><topic>Computer simulation</topic><topic>Coolant pumps</topic><topic>Deformation</topic><topic>Friction</topic><topic>High temperature</topic><topic>Inlet temperature</topic><topic>Leakage</topic><topic>Localization</topic><topic>Low pressure</topic><topic>Lubricants & lubrication</topic><topic>Nuclear energy</topic><topic>Nuclear power plants</topic><topic>Nuclear reactors</topic><topic>Nuclear safety</topic><topic>Sealing</topic><topic>Seals</topic><topic>Seals (stoppers)</topic><topic>Sensors</topic><topic>Water temperature</topic><topic>Working conditions</topic><toplevel>peer_reviewed</toplevel><toplevel>online_resources</toplevel><creatorcontrib>Gou, Qiuqin</creatorcontrib><creatorcontrib>Xiao, Shide</creatorcontrib><creatorcontrib>Chen, Xiaoming</creatorcontrib><collection>Hindawi Publishing Complete</collection><collection>Hindawi Publishing Subscription Journals</collection><collection>Hindawi Publishing Open Access</collection><collection>CrossRef</collection><collection>ProQuest Central (Corporate)</collection><collection>Electronics & Communications Abstracts</collection><collection>Solid State and Superconductivity Abstracts</collection><collection>ProQuest Central (purchase pre-March 2016)</collection><collection>Computing Database (Alumni Edition)</collection><collection>Technology Research Database</collection><collection>ProQuest SciTech Collection</collection><collection>ProQuest Technology Collection</collection><collection>ProQuest Central (Alumni) (purchase pre-March 2016)</collection><collection>Materials Science & Engineering Collection</collection><collection>ProQuest Central (Alumni Edition)</collection><collection>ProQuest Central UK/Ireland</collection><collection>Advanced Technologies & Aerospace Collection</collection><collection>ProQuest Central Essentials</collection><collection>ProQuest Central</collection><collection>Technology Collection</collection><collection>ProQuest One Community College</collection><collection>Middle East & Africa Database</collection><collection>ProQuest Materials Science Collection</collection><collection>ProQuest Central Korea</collection><collection>ProQuest Central Student</collection><collection>SciTech Premium Collection</collection><collection>ProQuest Computer Science Collection</collection><collection>Computer Science Database</collection><collection>Materials Science Database</collection><collection>ProQuest Engineering Collection</collection><collection>Advanced Technologies Database with Aerospace</collection><collection>Computing Database</collection><collection>Engineering Database</collection><collection>Advanced Technologies & Aerospace Database</collection><collection>ProQuest Advanced Technologies & Aerospace Collection</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>Engineering Collection</collection><collection>ProQuest Central Basic</collection><jtitle>Journal of sensors</jtitle></facets><delivery><delcategory>Remote Search Resource</delcategory><fulltext>fulltext</fulltext></delivery><addata><au>Gou, Qiuqin</au><au>Xiao, Shide</au><au>Chen, Xiaoming</au><au>Fan, Yaxiang</au><au>Yaxiang Fan</au><format>journal</format><genre>article</genre><ristype>JOUR</ristype><atitle>Friction Performance Analysis of Reactor Coolant Pump Shaft Seal Based on Sensor and Computer Simulation</atitle><jtitle>Journal of sensors</jtitle><date>2022-09-17</date><risdate>2022</risdate><volume>2022</volume><spage>1</spage><epage>11</epage><pages>1-11</pages><issn>1687-725X</issn><eissn>1687-7268</eissn><abstract>In recent years, the state has put forward a grand plan to develop nuclear power in order to control environmental pollution and carbon emissions. In nuclear power plants, mechanical seals for reactor coolant pump play an important role in nuclear power safety production. However, China cannot independently produce such mechanical seals, and they are blocked by foreign related technologies, which has seriously affected China’s nuclear power development plan and the overall safety of China’s nuclear power operation. Under this background, this paper studies the friction performance of the shaft seal of the reactor coolant pump, uses the sensor to obtain the data of friction factors such as low-pressure leakage, effectively monitors the low-pressure leakage through calculation and simulation modeling, truly reflects the operating state of the reactor coolant pump, and provides a new research direction and experimental basis for further analysis of the friction performance of the shaft seal of the reactor coolant pump. The results show that under the joint action of the pressure difference and the force generated by the deformation of the moving ring plate, the cone angle formed on the seal end face is 1300.9 μ convergence gap of rad. When the inlet water temperature is 65°C, the leakage rate is 1867.8 L/h. The deformation of the moving ring deformation ring plate can hinder the increase of the deformation cone angle of the moving ring. The greater the thickness of the moving ring deformation ring plate, the greater the seal leakage rate. The inlet temperature of the sealing medium and the friction performance of the material also have an impact on the sealing performance.</abstract><cop>New York</cop><pub>Hindawi</pub><doi>10.1155/2022/7838491</doi><tpages>11</tpages><orcidid>https://orcid.org/0000-0002-8835-5863</orcidid><oa>free_for_read</oa></addata></record> |
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subjects | Computer simulation Coolant pumps Deformation Friction High temperature Inlet temperature Leakage Localization Low pressure Lubricants & lubrication Nuclear energy Nuclear power plants Nuclear reactors Nuclear safety Sealing Seals Seals (stoppers) Sensors Water temperature Working conditions |
title | Friction Performance Analysis of Reactor Coolant Pump Shaft Seal Based on Sensor and Computer Simulation |
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