Reactor-following load adjusting method and system for nuclear energy heat supply unit
The invention relates to a nuclear energy heat supply unit reactor following machine load adjusting method and system. The nuclear energy heat supply unit reactor following machine load adjusting method comprises the steps that a heat supply unit steam turbine first-stage pressure signal and a steam...
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| creator | ZHANG BINGZHUO ZHANG HENAN WANG SHANSHAN CUI QINGLAN WANG XIANGYU XIE HONGJUN SONG DA CAI XIANGYANG XING ZHAOKAI CAO JIANYUAN LI JIANWEI YANG JINFENG XU GUOBIN ZHOU YONGFENG |
| description | The invention relates to a nuclear energy heat supply unit reactor following machine load adjusting method and system. The nuclear energy heat supply unit reactor following machine load adjusting method comprises the steps that a heat supply unit steam turbine first-stage pressure signal and a steam extraction heat supply flow signal are collected; the collected signals are preprocessed, and the load value of the steam turbine is determined based on the processed signals; and the reactor power of the heat supply unit is adjusted based on the steam turbine load value. According to the technical scheme provided by the invention, the problem of large deviation between the reactor power and the steam turbine load value in the unit heat supply operation process of a conventional logic loop is solved, the control accuracy is improved, and meanwhile, the system disturbance caused by potential curve switching manual operation errors during multi-curve mode operation is also solved; the fluctuation of the operation pa |
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The nuclear energy heat supply unit reactor following machine load adjusting method comprises the steps that a heat supply unit steam turbine first-stage pressure signal and a steam extraction heat supply flow signal are collected; the collected signals are preprocessed, and the load value of the steam turbine is determined based on the processed signals; and the reactor power of the heat supply unit is adjusted based on the steam turbine load value. According to the technical scheme provided by the invention, the problem of large deviation between the reactor power and the steam turbine load value in the unit heat supply operation process of a conventional logic loop is solved, the control accuracy is improved, and meanwhile, the system disturbance caused by potential curve switching manual operation errors during multi-curve mode operation is also solved; the fluctuation of the operation pa</description><language>chi ; eng</language><subject>BLASTING ; CALCULATING ; COMPUTING ; COUNTING ; ENGINE PLANTS IN GENERAL ; ENGINE PLANTS NOT OTHERWISE PROVIDED FOR ; ENGINES USING SPECIAL WORKING FLUIDS OR CYCLES ; HANDLING RECORD CARRIERS ; HEATING ; LIGHTING ; MACHINES OR ENGINES IN GENERAL ; MECHANICAL ENGINEERING ; NUCLEAR ENGINEERING ; NUCLEAR PHYSICS ; NUCLEAR POWER PLANT ; PHYSICS ; PRESENTATION OF DATA ; RECOGNITION OF DATA ; RECORD CARRIERS ; STEAM ACCUMULATORS ; STEAM ENGINE PLANTS ; STEAM ENGINES ; WEAPONS</subject><creationdate>2022</creationdate><oa>free_for_read</oa><woscitedreferencessubscribed>false</woscitedreferencessubscribed></display><links><openurl>$$Topenurl_article</openurl><openurlfulltext>$$Topenurlfull_article</openurlfulltext><thumbnail>$$Tsyndetics_thumb_exl</thumbnail><linktohtml>$$Uhttps://worldwide.espacenet.com/publicationDetails/biblio?FT=D&date=20220603&DB=EPODOC&CC=CN&NR=114575952A$$EHTML$$P50$$Gepo$$Hfree_for_read</linktohtml><link.rule.ids>230,308,776,881,25542,76290</link.rule.ids><linktorsrc>$$Uhttps://worldwide.espacenet.com/publicationDetails/biblio?FT=D&date=20220603&DB=EPODOC&CC=CN&NR=114575952A$$EView_record_in_European_Patent_Office$$FView_record_in_$$GEuropean_Patent_Office$$Hfree_for_read</linktorsrc></links><search><creatorcontrib>ZHANG BINGZHUO</creatorcontrib><creatorcontrib>ZHANG HENAN</creatorcontrib><creatorcontrib>WANG SHANSHAN</creatorcontrib><creatorcontrib>CUI QINGLAN</creatorcontrib><creatorcontrib>WANG XIANGYU</creatorcontrib><creatorcontrib>XIE HONGJUN</creatorcontrib><creatorcontrib>SONG DA</creatorcontrib><creatorcontrib>CAI XIANGYANG</creatorcontrib><creatorcontrib>XING ZHAOKAI</creatorcontrib><creatorcontrib>CAO JIANYUAN</creatorcontrib><creatorcontrib>LI JIANWEI</creatorcontrib><creatorcontrib>YANG JINFENG</creatorcontrib><creatorcontrib>XU GUOBIN</creatorcontrib><creatorcontrib>ZHOU YONGFENG</creatorcontrib><title>Reactor-following load adjusting method and system for nuclear energy heat supply unit</title><description>The invention relates to a nuclear energy heat supply unit reactor following machine load adjusting method and system. 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According to the technical scheme provided by the invention, the problem of large deviation between the reactor power and the steam turbine load value in the unit heat supply operation process of a conventional logic loop is solved, the control accuracy is improved, and meanwhile, the system disturbance caused by potential curve switching manual operation errors during multi-curve mode operation is also solved; the fluctuation of the operation pa</description><subject>BLASTING</subject><subject>CALCULATING</subject><subject>COMPUTING</subject><subject>COUNTING</subject><subject>ENGINE PLANTS IN GENERAL</subject><subject>ENGINE PLANTS NOT OTHERWISE PROVIDED FOR</subject><subject>ENGINES USING SPECIAL WORKING FLUIDS OR CYCLES</subject><subject>HANDLING RECORD CARRIERS</subject><subject>HEATING</subject><subject>LIGHTING</subject><subject>MACHINES OR ENGINES IN GENERAL</subject><subject>MECHANICAL ENGINEERING</subject><subject>NUCLEAR ENGINEERING</subject><subject>NUCLEAR PHYSICS</subject><subject>NUCLEAR POWER PLANT</subject><subject>PHYSICS</subject><subject>PRESENTATION OF DATA</subject><subject>RECOGNITION OF DATA</subject><subject>RECORD CARRIERS</subject><subject>STEAM ACCUMULATORS</subject><subject>STEAM ENGINE PLANTS</subject><subject>STEAM ENGINES</subject><subject>WEAPONS</subject><fulltext>true</fulltext><rsrctype>patent</rsrctype><creationdate>2022</creationdate><recordtype>patent</recordtype><sourceid>EVB</sourceid><recordid>eNqNizEKwkAQRbexEPUO4wFSRA2SUoJiZSFiG4ZkNolMdpbdWSS3N4IHsPq8x_tL87wTNiohs8Is78F1wIItYPtKUb84kvYyC9dCnKLSCFYCuNQwYQByFLoJekKFmLznCZIbdG0WFjnS5rcrs72cH9U1Iy81RY_NfNS6uuX5oTgWZbE77f9pPlaZOgU</recordid><startdate>20220603</startdate><enddate>20220603</enddate><creator>ZHANG BINGZHUO</creator><creator>ZHANG HENAN</creator><creator>WANG SHANSHAN</creator><creator>CUI QINGLAN</creator><creator>WANG XIANGYU</creator><creator>XIE HONGJUN</creator><creator>SONG DA</creator><creator>CAI XIANGYANG</creator><creator>XING ZHAOKAI</creator><creator>CAO JIANYUAN</creator><creator>LI JIANWEI</creator><creator>YANG JINFENG</creator><creator>XU GUOBIN</creator><creator>ZHOU YONGFENG</creator><scope>EVB</scope></search><sort><creationdate>20220603</creationdate><title>Reactor-following load adjusting method and system for nuclear energy heat supply unit</title><author>ZHANG BINGZHUO ; ZHANG HENAN ; WANG SHANSHAN ; CUI QINGLAN ; WANG XIANGYU ; XIE HONGJUN ; SONG DA ; CAI XIANGYANG ; XING ZHAOKAI ; CAO JIANYUAN ; LI JIANWEI ; YANG JINFENG ; XU GUOBIN ; ZHOU YONGFENG</author></sort><facets><frbrtype>5</frbrtype><frbrgroupid>cdi_FETCH-epo_espacenet_CN114575952A3</frbrgroupid><rsrctype>patents</rsrctype><prefilter>patents</prefilter><language>chi ; eng</language><creationdate>2022</creationdate><topic>BLASTING</topic><topic>CALCULATING</topic><topic>COMPUTING</topic><topic>COUNTING</topic><topic>ENGINE PLANTS IN GENERAL</topic><topic>ENGINE PLANTS NOT OTHERWISE PROVIDED FOR</topic><topic>ENGINES USING SPECIAL WORKING FLUIDS OR CYCLES</topic><topic>HANDLING RECORD CARRIERS</topic><topic>HEATING</topic><topic>LIGHTING</topic><topic>MACHINES OR ENGINES IN GENERAL</topic><topic>MECHANICAL ENGINEERING</topic><topic>NUCLEAR ENGINEERING</topic><topic>NUCLEAR PHYSICS</topic><topic>NUCLEAR POWER PLANT</topic><topic>PHYSICS</topic><topic>PRESENTATION OF DATA</topic><topic>RECOGNITION OF DATA</topic><topic>RECORD CARRIERS</topic><topic>STEAM ACCUMULATORS</topic><topic>STEAM ENGINE PLANTS</topic><topic>STEAM ENGINES</topic><topic>WEAPONS</topic><toplevel>online_resources</toplevel><creatorcontrib>ZHANG BINGZHUO</creatorcontrib><creatorcontrib>ZHANG HENAN</creatorcontrib><creatorcontrib>WANG SHANSHAN</creatorcontrib><creatorcontrib>CUI QINGLAN</creatorcontrib><creatorcontrib>WANG XIANGYU</creatorcontrib><creatorcontrib>XIE HONGJUN</creatorcontrib><creatorcontrib>SONG DA</creatorcontrib><creatorcontrib>CAI XIANGYANG</creatorcontrib><creatorcontrib>XING ZHAOKAI</creatorcontrib><creatorcontrib>CAO JIANYUAN</creatorcontrib><creatorcontrib>LI JIANWEI</creatorcontrib><creatorcontrib>YANG JINFENG</creatorcontrib><creatorcontrib>XU GUOBIN</creatorcontrib><creatorcontrib>ZHOU YONGFENG</creatorcontrib><collection>esp@cenet</collection></facets><delivery><delcategory>Remote Search Resource</delcategory><fulltext>fulltext_linktorsrc</fulltext></delivery><addata><au>ZHANG BINGZHUO</au><au>ZHANG HENAN</au><au>WANG SHANSHAN</au><au>CUI QINGLAN</au><au>WANG XIANGYU</au><au>XIE HONGJUN</au><au>SONG DA</au><au>CAI XIANGYANG</au><au>XING ZHAOKAI</au><au>CAO JIANYUAN</au><au>LI JIANWEI</au><au>YANG JINFENG</au><au>XU GUOBIN</au><au>ZHOU YONGFENG</au><format>patent</format><genre>patent</genre><ristype>GEN</ristype><title>Reactor-following load adjusting method and system for nuclear energy heat supply unit</title><date>2022-06-03</date><risdate>2022</risdate><abstract>The invention relates to a nuclear energy heat supply unit reactor following machine load adjusting method and system. The nuclear energy heat supply unit reactor following machine load adjusting method comprises the steps that a heat supply unit steam turbine first-stage pressure signal and a steam extraction heat supply flow signal are collected; the collected signals are preprocessed, and the load value of the steam turbine is determined based on the processed signals; and the reactor power of the heat supply unit is adjusted based on the steam turbine load value. According to the technical scheme provided by the invention, the problem of large deviation between the reactor power and the steam turbine load value in the unit heat supply operation process of a conventional logic loop is solved, the control accuracy is improved, and meanwhile, the system disturbance caused by potential curve switching manual operation errors during multi-curve mode operation is also solved; the fluctuation of the operation pa</abstract><oa>free_for_read</oa></addata></record> |
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| subjects | BLASTING CALCULATING COMPUTING COUNTING ENGINE PLANTS IN GENERAL ENGINE PLANTS NOT OTHERWISE PROVIDED FOR ENGINES USING SPECIAL WORKING FLUIDS OR CYCLES HANDLING RECORD CARRIERS HEATING LIGHTING MACHINES OR ENGINES IN GENERAL MECHANICAL ENGINEERING NUCLEAR ENGINEERING NUCLEAR PHYSICS NUCLEAR POWER PLANT PHYSICS PRESENTATION OF DATA RECOGNITION OF DATA RECORD CARRIERS STEAM ACCUMULATORS STEAM ENGINE PLANTS STEAM ENGINES WEAPONS |
| title | Reactor-following load adjusting method and system for nuclear energy heat supply unit |
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