JOP20190310A1 - طريقة لتبريد صهر مركز مفاعل نووي ونظام تحكم لتبريد صهر مركز مفاعل نووي - Google Patents

طريقة لتبريد صهر مركز مفاعل نووي ونظام تحكم لتبريد صهر مركز مفاعل نووي

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Publication number
JOP20190310A1
JOP20190310A1 JOP/2019/0310A JOP20190310A JOP20190310A1 JO P20190310 A1 JOP20190310 A1 JO P20190310A1 JO P20190310 A JOP20190310 A JO P20190310A JO P20190310 A1 JOP20190310 A1 JO P20190310A1
Authority
JO
Jordan
Prior art keywords
reactor
cooling
molten core
molten
technical result
Prior art date
Application number
JOP/2019/0310A
Other languages
English (en)
Inventor
Aleksandr Stalevich Sidorov
Nadezhda Vasilevna Sidorova
Original Assignee
Joint Stock Company Science And Innovations
Joint Stock Company Atomenergoproekt
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 Science And Innovations, Joint Stock Company Atomenergoproekt filed Critical Joint Stock Company Science And Innovations
Publication of JOP20190310A1 publication Critical patent/JOP20190310A1/ar
Application granted granted Critical
Publication of JOP20190310B1 publication Critical patent/JOP20190310B1/ar

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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

يتعلق الاختراع بالأنظمة لضمان التشغيل الآمن لمحطات الطاقة النووية في الحوادث الشديدة، على وجه الخصوص، بطرق ونظم التبريد والتحكم في تبريد صهر المفاعلات النووية. والنتيجة التقنية للاختراعات المطالب بها هي زيادة سلامة محطات الطاقة النووية، وكفاءة التبريد لصهر اللب للمفاعل النووي. تتمثل المهمة التي توجه إليها الاختراعات المطالب بها في زيادة كفاءة تبريد صهر اللب لمفاعل نووي عن طريق إزالة الحمل الحراري بأمان من مرآة الصهر، وضمان القضاء على الانفجارات البخارية التي تؤدي إلى تدمير منطقة انتشار من الحوادث، ومنجم المفاعل وبناء احتواءه. يتم تحقيق النتيجة الفنية عن طريق تغيير مبدأ تبريد صهر اللب المفاعل النووي، والذي يتكون في حقيقة أنه بعد تدمير لب وعاء المفاعل بواسطة الصهر، يتم تحديد شروط التبريد اللاحق للصهر بخصائص جسم الماسك الاساسي، وليس بواسطة مفاعل نووي. بالإضافة إلى ذلك ، يتم تحقيق النتيجة الفنية من خلال تركيب أجهزة استشعار درجة الحرارة ، وأجهزة استشعار مستوى مصممة لرصد عملية التبريد من صهرالمفاعل النووي. 3 الرسومات، 2 فقرات
JOP/2019/0310A 2018-11-01 2018-12-28 طريقة لتبريد صهر مركز مفاعل نووي ونظام تحكم لتبريد صهر مركز مفاعل نووي JOP20190310B1 (ar)

Applications Claiming Priority (2)

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
PCT/RU2018/000897 WO2020091623A1 (ru) 2018-11-01 2018-12-28 Способ охлаждения расплава активной зоны ядерного реактора и система контроля охлаждения расплава активной зоны ядерного реактора

Publications (2)

Publication Number Publication Date
JOP20190310A1 true JOP20190310A1 (ar) 2020-05-01
JOP20190310B1 JOP20190310B1 (ar) 2023-09-17

Family

ID=67733893

Family Applications (1)

Application Number Title Priority Date Filing Date
JOP/2019/0310A JOP20190310B1 (ar) 2018-11-01 2018-12-28 طريقة لتبريد صهر مركز مفاعل نووي ونظام تحكم لتبريد صهر مركز مفاعل نووي

Country Status (11)

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

Families Citing this family (5)

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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 (ar) * 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
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
AR116950A1 (es) 2021-06-30
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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