METHOD AND SYSTEM FOR BRINGING A NUCLEAR POWER PLANT INTO A SAFE STATE AFTER EXTREME EFFECT
The method and system for bringing a nuclear power plant to a safe state after extreme effect reduce the temperature of the coolant after extreme effect. The system includes inlet and outlet pipelines (3, 9), a steam generator (1), a storage tank (8) and a heat exchanger (11), a separation tank (4)...
Gespeichert in:
| Hauptverfasser: | , , , , , , , , , , , |
|---|---|
| Format: | Patent |
| Sprache: | eng |
| Schlagworte: | |
| Online-Zugang: | Volltext bestellen |
| Tags: |
Tag hinzufügen
Keine Tags, Fügen Sie den ersten Tag hinzu!
|
| container_end_page | |
|---|---|
| container_issue | |
| container_start_page | |
| container_title | |
| container_volume | |
| creator | TRETYAKOV, Evgenij Aleksandrovich MEZENIN, Evgenij Igorevich BEZLEPKIN Vladimir Viktorovich ALTBREGEN, Darya Robertovna KOZLOV, Vyacheslav Borisovich SHIRVANYANC, Anton Eduardovich LUKINA, Anzhela Vasilevna NOSANKOVA, Lajne Vyajnovna VIBE, Dmitrij Yakovlevich GAVRILOV Maksim Vladimirovich EGOROV, Evgenij Yurevich OBRAZCOV, Evgenij Pavlovich |
| description | The method and system for bringing a nuclear power plant to a safe state after extreme effect reduce the temperature of the coolant after extreme effect. The system includes inlet and outlet pipelines (3, 9), a steam generator (1), a storage tank (8) and a heat exchanger (11), a separation tank (4) above the steam generator (1) and connected by two pipelines to a storage tank (8), a pump (10), a control unit. The method involves filling the system with coolant, feeding the coolant from the steam generator (1) through the inlet pipeline (3) and the storage tank (8) to the heat exchanger (11), and feeding the coolant through the outlet pipeline (9) back to the steam generator (1), wherein the pump (10) is turned on for feeding the coolant and subsequent operation of the system. The first air valve (7) is used to maintain pressure in the system, ensuring the absence of boiling of the coolant. |
| format | Patent |
| fullrecord | <record><control><sourceid>epo_EVB</sourceid><recordid>TN_cdi_epo_espacenet_MY202361A</recordid><sourceformat>XML</sourceformat><sourcesystem>PC</sourcesystem><sourcerecordid>MY202361A</sourcerecordid><originalsourceid>FETCH-epo_espacenet_MY202361A3</originalsourceid><addsrcrecordid>eNqFirEKwjAURbM4iPoL8n5A0Bbcn-mNLTSJJE-0OJQicRIt1P_HDO7C5Zzh3Lm6WUjtK2JXUeyiwJLxgQ6hccc8YnJn3YIDnfwFmS07ocaJzymyAUVhAbGRXHGVAAuCMdCyVLPH8JzS6ueFWhuIrjdpfPdpGod7eqVPb7tiW5T7HZd_D18hdjBd</addsrcrecordid><sourcetype>Open Access Repository</sourcetype><iscdi>true</iscdi><recordtype>patent</recordtype></control><display><type>patent</type><title>METHOD AND SYSTEM FOR BRINGING A NUCLEAR POWER PLANT INTO A SAFE STATE AFTER EXTREME EFFECT</title><source>esp@cenet</source><creator>TRETYAKOV, Evgenij Aleksandrovich ; MEZENIN, Evgenij Igorevich ; BEZLEPKIN Vladimir Viktorovich ; ALTBREGEN, Darya Robertovna ; KOZLOV, Vyacheslav Borisovich ; SHIRVANYANC, Anton Eduardovich ; LUKINA, Anzhela Vasilevna ; NOSANKOVA, Lajne Vyajnovna ; VIBE, Dmitrij Yakovlevich ; GAVRILOV Maksim Vladimirovich ; EGOROV, Evgenij Yurevich ; OBRAZCOV, Evgenij Pavlovich</creator><creatorcontrib>TRETYAKOV, Evgenij Aleksandrovich ; MEZENIN, Evgenij Igorevich ; BEZLEPKIN Vladimir Viktorovich ; ALTBREGEN, Darya Robertovna ; KOZLOV, Vyacheslav Borisovich ; SHIRVANYANC, Anton Eduardovich ; LUKINA, Anzhela Vasilevna ; NOSANKOVA, Lajne Vyajnovna ; VIBE, Dmitrij Yakovlevich ; GAVRILOV Maksim Vladimirovich ; EGOROV, Evgenij Yurevich ; OBRAZCOV, Evgenij Pavlovich</creatorcontrib><description>The method and system for bringing a nuclear power plant to a safe state after extreme effect reduce the temperature of the coolant after extreme effect. The system includes inlet and outlet pipelines (3, 9), a steam generator (1), a storage tank (8) and a heat exchanger (11), a separation tank (4) above the steam generator (1) and connected by two pipelines to a storage tank (8), a pump (10), a control unit. The method involves filling the system with coolant, feeding the coolant from the steam generator (1) through the inlet pipeline (3) and the storage tank (8) to the heat exchanger (11), and feeding the coolant through the outlet pipeline (9) back to the steam generator (1), wherein the pump (10) is turned on for feeding the coolant and subsequent operation of the system. The first air valve (7) is used to maintain pressure in the system, ensuring the absence of boiling of the coolant.</description><language>eng</language><subject>NUCLEAR ENGINEERING ; NUCLEAR PHYSICS ; NUCLEAR REACTORS ; PHYSICS</subject><creationdate>2024</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=20240424&DB=EPODOC&CC=MY&NR=202361A$$EHTML$$P50$$Gepo$$Hfree_for_read</linktohtml><link.rule.ids>230,308,777,882,25545,76296</link.rule.ids><linktorsrc>$$Uhttps://worldwide.espacenet.com/publicationDetails/biblio?FT=D&date=20240424&DB=EPODOC&CC=MY&NR=202361A$$EView_record_in_European_Patent_Office$$FView_record_in_$$GEuropean_Patent_Office$$Hfree_for_read</linktorsrc></links><search><creatorcontrib>TRETYAKOV, Evgenij Aleksandrovich</creatorcontrib><creatorcontrib>MEZENIN, Evgenij Igorevich</creatorcontrib><creatorcontrib>BEZLEPKIN Vladimir Viktorovich</creatorcontrib><creatorcontrib>ALTBREGEN, Darya Robertovna</creatorcontrib><creatorcontrib>KOZLOV, Vyacheslav Borisovich</creatorcontrib><creatorcontrib>SHIRVANYANC, Anton Eduardovich</creatorcontrib><creatorcontrib>LUKINA, Anzhela Vasilevna</creatorcontrib><creatorcontrib>NOSANKOVA, Lajne Vyajnovna</creatorcontrib><creatorcontrib>VIBE, Dmitrij Yakovlevich</creatorcontrib><creatorcontrib>GAVRILOV Maksim Vladimirovich</creatorcontrib><creatorcontrib>EGOROV, Evgenij Yurevich</creatorcontrib><creatorcontrib>OBRAZCOV, Evgenij Pavlovich</creatorcontrib><title>METHOD AND SYSTEM FOR BRINGING A NUCLEAR POWER PLANT INTO A SAFE STATE AFTER EXTREME EFFECT</title><description>The method and system for bringing a nuclear power plant to a safe state after extreme effect reduce the temperature of the coolant after extreme effect. The system includes inlet and outlet pipelines (3, 9), a steam generator (1), a storage tank (8) and a heat exchanger (11), a separation tank (4) above the steam generator (1) and connected by two pipelines to a storage tank (8), a pump (10), a control unit. The method involves filling the system with coolant, feeding the coolant from the steam generator (1) through the inlet pipeline (3) and the storage tank (8) to the heat exchanger (11), and feeding the coolant through the outlet pipeline (9) back to the steam generator (1), wherein the pump (10) is turned on for feeding the coolant and subsequent operation of the system. The first air valve (7) is used to maintain pressure in the system, ensuring the absence of boiling of the coolant.</description><subject>NUCLEAR ENGINEERING</subject><subject>NUCLEAR PHYSICS</subject><subject>NUCLEAR REACTORS</subject><subject>PHYSICS</subject><fulltext>true</fulltext><rsrctype>patent</rsrctype><creationdate>2024</creationdate><recordtype>patent</recordtype><sourceid>EVB</sourceid><recordid>eNqFirEKwjAURbM4iPoL8n5A0Bbcn-mNLTSJJE-0OJQicRIt1P_HDO7C5Zzh3Lm6WUjtK2JXUeyiwJLxgQ6hccc8YnJn3YIDnfwFmS07ocaJzymyAUVhAbGRXHGVAAuCMdCyVLPH8JzS6ueFWhuIrjdpfPdpGod7eqVPb7tiW5T7HZd_D18hdjBd</recordid><startdate>20240424</startdate><enddate>20240424</enddate><creator>TRETYAKOV, Evgenij Aleksandrovich</creator><creator>MEZENIN, Evgenij Igorevich</creator><creator>BEZLEPKIN Vladimir Viktorovich</creator><creator>ALTBREGEN, Darya Robertovna</creator><creator>KOZLOV, Vyacheslav Borisovich</creator><creator>SHIRVANYANC, Anton Eduardovich</creator><creator>LUKINA, Anzhela Vasilevna</creator><creator>NOSANKOVA, Lajne Vyajnovna</creator><creator>VIBE, Dmitrij Yakovlevich</creator><creator>GAVRILOV Maksim Vladimirovich</creator><creator>EGOROV, Evgenij Yurevich</creator><creator>OBRAZCOV, Evgenij Pavlovich</creator><scope>EVB</scope></search><sort><creationdate>20240424</creationdate><title>METHOD AND SYSTEM FOR BRINGING A NUCLEAR POWER PLANT INTO A SAFE STATE AFTER EXTREME EFFECT</title><author>TRETYAKOV, Evgenij Aleksandrovich ; MEZENIN, Evgenij Igorevich ; BEZLEPKIN Vladimir Viktorovich ; ALTBREGEN, Darya Robertovna ; KOZLOV, Vyacheslav Borisovich ; SHIRVANYANC, Anton Eduardovich ; LUKINA, Anzhela Vasilevna ; NOSANKOVA, Lajne Vyajnovna ; VIBE, Dmitrij Yakovlevich ; GAVRILOV Maksim Vladimirovich ; EGOROV, Evgenij Yurevich ; OBRAZCOV, Evgenij Pavlovich</author></sort><facets><frbrtype>5</frbrtype><frbrgroupid>cdi_FETCH-epo_espacenet_MY202361A3</frbrgroupid><rsrctype>patents</rsrctype><prefilter>patents</prefilter><language>eng</language><creationdate>2024</creationdate><topic>NUCLEAR ENGINEERING</topic><topic>NUCLEAR PHYSICS</topic><topic>NUCLEAR REACTORS</topic><topic>PHYSICS</topic><toplevel>online_resources</toplevel><creatorcontrib>TRETYAKOV, Evgenij Aleksandrovich</creatorcontrib><creatorcontrib>MEZENIN, Evgenij Igorevich</creatorcontrib><creatorcontrib>BEZLEPKIN Vladimir Viktorovich</creatorcontrib><creatorcontrib>ALTBREGEN, Darya Robertovna</creatorcontrib><creatorcontrib>KOZLOV, Vyacheslav Borisovich</creatorcontrib><creatorcontrib>SHIRVANYANC, Anton Eduardovich</creatorcontrib><creatorcontrib>LUKINA, Anzhela Vasilevna</creatorcontrib><creatorcontrib>NOSANKOVA, Lajne Vyajnovna</creatorcontrib><creatorcontrib>VIBE, Dmitrij Yakovlevich</creatorcontrib><creatorcontrib>GAVRILOV Maksim Vladimirovich</creatorcontrib><creatorcontrib>EGOROV, Evgenij Yurevich</creatorcontrib><creatorcontrib>OBRAZCOV, Evgenij Pavlovich</creatorcontrib><collection>esp@cenet</collection></facets><delivery><delcategory>Remote Search Resource</delcategory><fulltext>fulltext_linktorsrc</fulltext></delivery><addata><au>TRETYAKOV, Evgenij Aleksandrovich</au><au>MEZENIN, Evgenij Igorevich</au><au>BEZLEPKIN Vladimir Viktorovich</au><au>ALTBREGEN, Darya Robertovna</au><au>KOZLOV, Vyacheslav Borisovich</au><au>SHIRVANYANC, Anton Eduardovich</au><au>LUKINA, Anzhela Vasilevna</au><au>NOSANKOVA, Lajne Vyajnovna</au><au>VIBE, Dmitrij Yakovlevich</au><au>GAVRILOV Maksim Vladimirovich</au><au>EGOROV, Evgenij Yurevich</au><au>OBRAZCOV, Evgenij Pavlovich</au><format>patent</format><genre>patent</genre><ristype>GEN</ristype><title>METHOD AND SYSTEM FOR BRINGING A NUCLEAR POWER PLANT INTO A SAFE STATE AFTER EXTREME EFFECT</title><date>2024-04-24</date><risdate>2024</risdate><abstract>The method and system for bringing a nuclear power plant to a safe state after extreme effect reduce the temperature of the coolant after extreme effect. The system includes inlet and outlet pipelines (3, 9), a steam generator (1), a storage tank (8) and a heat exchanger (11), a separation tank (4) above the steam generator (1) and connected by two pipelines to a storage tank (8), a pump (10), a control unit. The method involves filling the system with coolant, feeding the coolant from the steam generator (1) through the inlet pipeline (3) and the storage tank (8) to the heat exchanger (11), and feeding the coolant through the outlet pipeline (9) back to the steam generator (1), wherein the pump (10) is turned on for feeding the coolant and subsequent operation of the system. The first air valve (7) is used to maintain pressure in the system, ensuring the absence of boiling of the coolant.</abstract><oa>free_for_read</oa></addata></record> |
| fulltext | fulltext_linktorsrc |
| identifier | |
| ispartof | |
| issn | |
| language | eng |
| recordid | cdi_epo_espacenet_MY202361A |
| source | esp@cenet |
| subjects | NUCLEAR ENGINEERING NUCLEAR PHYSICS NUCLEAR REACTORS PHYSICS |
| title | METHOD AND SYSTEM FOR BRINGING A NUCLEAR POWER PLANT INTO A SAFE STATE AFTER EXTREME EFFECT |
| url | https://sfx.bib-bvb.de/sfx_tum?ctx_ver=Z39.88-2004&ctx_enc=info:ofi/enc:UTF-8&ctx_tim=2025-01-21T08%3A45%3A40IST&url_ver=Z39.88-2004&url_ctx_fmt=infofi/fmt:kev:mtx:ctx&rfr_id=info:sid/primo.exlibrisgroup.com:primo3-Article-epo_EVB&rft_val_fmt=info:ofi/fmt:kev:mtx:patent&rft.genre=patent&rft.au=TRETYAKOV,%20Evgenij%20Aleksandrovich&rft.date=2024-04-24&rft_id=info:doi/&rft_dat=%3Cepo_EVB%3EMY202361A%3C/epo_EVB%3E%3Curl%3E%3C/url%3E&disable_directlink=true&sfx.directlink=off&sfx.report_link=0&rft_id=info:oai/&rft_id=info:pmid/&rfr_iscdi=true |