AR116950A1 - Método de enfriamiento de la base del reactor nuclear de fusión y sistema de control de enfriamiento de la base del reactor nuclear de fusión - Google Patents

Método de enfriamiento de la base del reactor nuclear de fusión y sistema de control de enfriamiento de la base del reactor nuclear de fusión

Info

Publication number
AR116950A1
AR116950A1 ARP190103186A ARP190103186A AR116950A1 AR 116950 A1 AR116950 A1 AR 116950A1 AR P190103186 A ARP190103186 A AR P190103186A AR P190103186 A ARP190103186 A AR P190103186A AR 116950 A1 AR116950 A1 AR 116950A1
Authority
AR
Argentina
Prior art keywords
fusion
nuclear
nuclear reactor
cooling
base
Prior art date
Application number
ARP190103186A
Other languages
English (en)
Inventor
Nadezhda Vasilevna Sidorova
Aleksandr Stalevich Sidorov
Original Assignee
Joint Stock Company “Atomenergoproekt”
Joint Stock Company Science And Innovations
Priority date (The priority date is an assumption and is not a legal conclusion. Google has not performed a legal analysis and makes no representation as to the accuracy of the date listed.)
Filing date
Publication date
Application filed by Joint Stock Company “Atomenergoproekt”, Joint Stock Company Science And Innovations filed Critical Joint Stock Company “Atomenergoproekt”
Publication of AR116950A1 publication Critical patent/AR116950A1/es

Links

Classifications

    • G—PHYSICS
    • G21—NUCLEAR PHYSICS; NUCLEAR ENGINEERING
    • G21C—NUCLEAR REACTORS
    • G21C15/00—Cooling arrangements within the pressure vessel containing the core; Selection of specific coolants
    • G21C15/18—Emergency cooling arrangements; Removing shut-down heat
    • G—PHYSICS
    • G21—NUCLEAR PHYSICS; NUCLEAR ENGINEERING
    • G21C—NUCLEAR REACTORS
    • G21C9/00—Emergency protection arrangements structurally associated with the reactor, e.g. safety valves provided with pressure equalisation devices
    • G21C9/016—Core catchers
    • G—PHYSICS
    • G21—NUCLEAR PHYSICS; NUCLEAR ENGINEERING
    • G21C—NUCLEAR REACTORS
    • G21C17/00—Monitoring; Testing ; Maintaining
    • G—PHYSICS
    • G21—NUCLEAR PHYSICS; NUCLEAR ENGINEERING
    • G21C—NUCLEAR REACTORS
    • G21C17/00—Monitoring; Testing ; Maintaining
    • G21C17/02—Devices or arrangements for monitoring coolant or moderator
    • G21C17/022—Devices or arrangements for monitoring coolant or moderator for monitoring liquid coolants or moderators
    • G—PHYSICS
    • G21—NUCLEAR PHYSICS; NUCLEAR ENGINEERING
    • G21C—NUCLEAR REACTORS
    • G21C17/00—Monitoring; Testing ; Maintaining
    • G21C17/10—Structural combination of fuel element, control rod, reactor core, or moderator structure with sensitive instruments, e.g. for measuring radioactivity, strain
    • G21C17/112—Measuring temperature
    • G—PHYSICS
    • G21—NUCLEAR PHYSICS; NUCLEAR ENGINEERING
    • G21C—NUCLEAR REACTORS
    • G21C19/00—Arrangements for treating, for handling, or for facilitating the handling of, fuel or other materials which are used within the reactor, e.g. within its pressure vessel
    • G21C19/02—Details of handling arrangements
    • G21C19/04—Means for controlling flow of coolant over objects being handled; Means for controlling flow of coolant through channel being serviced, e.g. for preventing "blow-out"
    • G—PHYSICS
    • G21—NUCLEAR PHYSICS; NUCLEAR ENGINEERING
    • G21C—NUCLEAR REACTORS
    • G21C19/00—Arrangements for treating, for handling, or for facilitating the handling of, fuel or other materials which are used within the reactor, e.g. within its pressure vessel
    • G21C19/28—Arrangements for introducing fluent material into the reactor core; Arrangements for removing fluent material from the reactor core
    • G21C19/30—Arrangements for introducing fluent material into the reactor core; Arrangements for removing fluent material from the reactor core with continuous purification of circulating fluent material, e.g. by extraction of fission products deterioration or corrosion products, impurities, e.g. by cold traps
    • G21C19/307—Arrangements for introducing fluent material into the reactor core; Arrangements for removing fluent material from the reactor core with continuous purification of circulating fluent material, e.g. by extraction of fission products deterioration or corrosion products, impurities, e.g. by cold traps specially adapted for liquids
    • G21C19/31—Arrangements for introducing fluent material into the reactor core; Arrangements for removing fluent material from the reactor core with continuous purification of circulating fluent material, e.g. by extraction of fission products deterioration or corrosion products, impurities, e.g. by cold traps specially adapted for liquids for molten metals
    • G21C19/313—Arrangements for introducing fluent material into the reactor core; Arrangements for removing fluent material from the reactor core with continuous purification of circulating fluent material, e.g. by extraction of fission products deterioration or corrosion products, impurities, e.g. by cold traps specially adapted for liquids for molten metals using cold traps
    • G—PHYSICS
    • G21—NUCLEAR PHYSICS; NUCLEAR ENGINEERING
    • G21C—NUCLEAR REACTORS
    • G21C9/00—Emergency protection arrangements structurally associated with the reactor, e.g. safety valves provided with pressure equalisation devices
    • G21C9/001—Emergency protection arrangements structurally associated with the reactor, e.g. safety valves provided with pressure equalisation devices against explosions, e.g. blast shields
    • Y—GENERAL TAGGING OF NEW TECHNOLOGICAL DEVELOPMENTS; GENERAL TAGGING OF CROSS-SECTIONAL TECHNOLOGIES SPANNING OVER SEVERAL SECTIONS OF THE IPC; TECHNICAL SUBJECTS COVERED BY FORMER USPC CROSS-REFERENCE ART COLLECTIONS [XRACs] AND DIGESTS
    • Y02—TECHNOLOGIES OR APPLICATIONS FOR MITIGATION OR ADAPTATION AGAINST CLIMATE CHANGE
    • Y02E—REDUCTION OF GREENHOUSE GAS [GHG] EMISSIONS, RELATED TO ENERGY GENERATION, TRANSMISSION OR DISTRIBUTION
    • Y02E30/00—Energy generation of nuclear origin
    • Y02E30/30—Nuclear fission reactors

Landscapes

  • Physics & Mathematics (AREA)
  • Engineering & Computer Science (AREA)
  • Plasma & Fusion (AREA)
  • General Engineering & Computer Science (AREA)
  • High Energy & Nuclear Physics (AREA)
  • Structure Of Emergency Protection For Nuclear Reactors (AREA)
  • Monitoring And Testing Of Nuclear Reactors (AREA)

Abstract

Las presentes se refieren a los sistemas de seguridad de las centrales nucleares (centrales nucleares) en caso de accidentes graves, concretamente a los métodos y sistemas de refrigeración y control de la fusión de la zona activa de los reactores nucleares. El resultado técnico de las presentes declaradas es mejorar la seguridad de la central nuclear, la eficiencia del enfriamiento de la fusión de la base del reactor nuclear. La tarea a la que se dirigen las presentes declaradas es mejorar la eficiencia de enfriamiento de la zona de fusión del reactor nuclear mediante la eliminación segura de la carga térmica del espejo de fusión, lo que garantiza la eliminación de las explosiones de vapor que conducen a la destrucción de la zona de localización de accidentes, la mina del reactor y el cañón hermético. El resultado técnico se logra cambiando el principio de enfriamiento de la fusión de la base nuclear, que es que después de la destrucción de la base fundida del cuerpo del reactor nuclear, las condiciones para el enfriamiento posterior de la fusión determinan las características del cuerpo de la trampa de fusión, no el reactor nuclear. Además, el resultado técnico se logra mediante un esquema de instalación de sensores de temperatura y sensores de nivel diseñados para controlar el proceso de enfriamiento de la fusión de la base del reactor nuclear.
ARP190103186A 2018-11-01 2019-10-31 Método de enfriamiento de la base del reactor nuclear de fusión y sistema de control de enfriamiento de la base del reactor nuclear de fusión AR116950A1 (es)

Applications Claiming Priority (1)

Application Number Priority Date Filing Date Title
RU2018138641A RU2698462C1 (ru) 2018-11-01 2018-11-01 Способ охлаждения расплава активной зоны ядерного реактора и система контроля охлаждения расплава активной зоны ядерного реактора

Publications (1)

Publication Number Publication Date
AR116950A1 true AR116950A1 (es) 2021-06-30

Family

ID=67733893

Family Applications (1)

Application Number Title Priority Date Filing Date
ARP190103186A AR116950A1 (es) 2018-11-01 2019-10-31 Método de enfriamiento de la base del reactor nuclear de fusión y sistema de control de enfriamiento de la base del reactor nuclear de fusión

Country Status (11)

Country Link
US (1) US11476010B2 (es)
EP (1) EP3876243A4 (es)
JP (1) JP7255778B2 (es)
KR (1) KR102422554B1 (es)
CN (1) CN111386577B (es)
AR (1) AR116950A1 (es)
BR (1) BR112019028268B1 (es)
EA (1) EA201992737A1 (es)
JO (1) JOP20190310B1 (es)
RU (1) RU2698462C1 (es)
WO (1) WO2020091623A1 (es)

Families Citing this family (5)

* Cited by examiner, † Cited by third party
Publication number Priority date Publication date Assignee Title
CN113450933B (zh) * 2021-08-19 2024-05-14 中国原子能科学研究院 反应堆余热排出系统及方法
CN114068052A (zh) * 2021-11-30 2022-02-18 中国核动力研究设计院 一种压水堆堆腔温度监测系统
CN115346700A (zh) * 2022-08-26 2022-11-15 核工业西南物理研究院 一种反应堆温度历史检测方法及检测装置
CN115470723B (zh) * 2022-08-31 2023-04-28 中国核动力研究设计院 一种获取水射流刺破熔池液面临界条件的方法
CN115565707B (zh) * 2022-10-08 2023-06-06 中国核动力研究设计院 堆芯熔融物安全壳滞留系统和收集体的参数设计方法

Family Cites Families (16)

* Cited by examiner, † Cited by third party
Publication number Priority date Publication date Assignee Title
DE8816470U1 (es) * 1988-05-17 1989-09-07 Siemens Ag, 1000 Berlin Und 8000 Muenchen, De
IT1251760B (it) * 1991-11-05 1995-05-23 Ente Naz Energia Elettrica Metodo per la protezione dell'integrita' del fondo del contenitore di un reattore in centrali nucleari e dispositivo per l'attuazione del metodo
FR2738662B1 (fr) * 1995-09-11 1997-12-05 Atea Dispositif de detection et de surveillance du percement du fond de la cuve d'un reacteur nucleaire comportant au moins un thermocouple
FR2784785B1 (fr) * 1998-10-14 2000-12-01 Commissariat Energie Atomique Reacteur nucleaire a eau equipe d'un receptacle contenant des structures internes deformables
RU2253914C2 (ru) * 2003-08-18 2005-06-10 Хабенский Владимир Бенцианович Система локализации и охлаждения кориума аварийного ядерного реактора водо-водяного типа
WO2007030224A2 (en) * 2005-07-27 2007-03-15 Battelle Memorial Institute A proliferation-resistant nuclear reactor
RU100328U1 (ru) * 2010-06-17 2010-12-10 Открытое акционерное общество "Санкт-Петербургский научно-исследовательский и проектно-конструкторский институт "АТОМЭНЕРГОПРОЕКТ" (ОАО "СПбАЭП) Система пассивного отвода тепла от теплообменника устройства локализации расплава
CN202102730U (zh) * 2011-05-09 2012-01-04 中科华核电技术研究院有限公司 反应堆严重事故堆芯熔融物堆外冷却固化装置及系统
US9251920B2 (en) * 2012-04-11 2016-02-02 Ge-Hitachi Nuclear Energy America Llc In-situ and external nuclear reactor severe accident temperature and water level probes
RU2514419C2 (ru) * 2012-06-01 2014-04-27 Открытое акционерное общество "Восточно-Европейский головной научно-исследовательский и проектный институт энергетических технологий" (ОАО "Головной институт "ВНИПИЭТ" Устройство локализации и охлаждения кориума ядерного реактора
CN103050155B (zh) * 2012-11-06 2015-12-02 国家核电技术有限公司 事故缓解装置及其制造方法、核电站压力容器、事故缓解方法
RU2576516C1 (ru) * 2014-12-16 2016-03-10 Акционерное Общество "Атомэнергопроект" Система локализации и охлаждения расплава активной зоны ядерного реактора водоводяного типа
MY196713A (en) * 2014-12-16 2023-05-02 Joint Stock Company Atomenergoproekt Water-cooled water-moderated nuclear reactor core melt cooling and confinement system
CN106651217B (zh) * 2017-01-06 2020-05-05 中国核动力研究设计院 装备堆芯捕集器的核电厂的堆芯注水评价方法
CN107808230A (zh) * 2017-09-28 2018-03-16 上海核工程研究设计院有限公司 一种核电厂堆芯损伤评价方法
CN107945891B (zh) * 2017-10-19 2021-01-19 中国核电工程有限公司 一种具有反应堆堆芯熔融物堆内滞留和堆外滞留功能的系统

Also Published As

Publication number Publication date
CN111386577A (zh) 2020-07-07
JOP20190310B1 (ar) 2023-09-17
JP2022511137A (ja) 2022-01-31
JOP20190310A1 (ar) 2020-05-01
EP3876243A4 (en) 2022-08-03
BR112019028268A2 (pt) 2021-05-11
KR102422554B1 (ko) 2022-07-20
WO2020091623A1 (ru) 2020-05-07
EP3876243A1 (en) 2021-09-08
US11476010B2 (en) 2022-10-18
RU2698462C1 (ru) 2019-08-27
EA201992737A1 (ru) 2020-09-14
BR112019028268B1 (pt) 2023-12-05
JP7255778B2 (ja) 2023-04-11
KR20200104213A (ko) 2020-09-03
US20210358648A1 (en) 2021-11-18
CN111386577B (zh) 2023-07-07

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