JOP20190307B1 - قلب المفاعل - Google Patents

قلب المفاعل

Info

Publication number
JOP20190307B1
JOP20190307B1 JOP/2019/0307A JOP20190307A JOP20190307B1 JO P20190307 B1 JOP20190307 B1 JO P20190307B1 JO P20190307 A JOP20190307 A JO P20190307A JO P20190307 B1 JOP20190307 B1 JO P20190307B1
Authority
JO
Jordan
Prior art keywords
casing
module
heat pipe
neutron
solid
Prior art date
Application number
JOP/2019/0307A
Other languages
English (en)
Inventor
Nikolay Ivanovich Loginov
Aleksey Dmitrievich Krotov
Aleksandr Sergeevich Mikheev
Original Assignee
Joint Stock Company Science And Innovations
Joint Stock Company State Scient Centre Of The Russian Federation Institute For Physics And Power En
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 State Scient Centre Of The Russian Federation Institute For Physics And Power En filed Critical Joint Stock Company Science And Innovations
Publication of JOP20190307A1 publication Critical patent/JOP20190307A1/ar
Application granted granted Critical
Publication of JOP20190307B1 publication Critical patent/JOP20190307B1/ar

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
    • G21C15/24—Promoting flow of the coolant
    • G21C15/257—Promoting flow of the coolant using heat-pipes
    • G—PHYSICS
    • G21—NUCLEAR PHYSICS; NUCLEAR ENGINEERING
    • G21C—NUCLEAR REACTORS
    • G21C5/00—Moderator or core structure; Selection of materials for use as moderator
    • G21C5/02—Details
    • G—PHYSICS
    • G21—NUCLEAR PHYSICS; NUCLEAR ENGINEERING
    • G21C—NUCLEAR REACTORS
    • G21C1/00—Reactor types
    • G21C1/04—Thermal reactors ; Epithermal reactors
    • G21C1/06—Heterogeneous reactors, i.e. in which fuel and moderator are separated
    • G21C1/08—Heterogeneous reactors, i.e. in which fuel and moderator are separated moderator being highly pressurised, e.g. boiling water reactor, integral super-heat reactor, pressurised water reactor
    • G21C1/10—Heterogeneous reactors, i.e. in which fuel and moderator are separated moderator being highly pressurised, e.g. boiling water reactor, integral super-heat reactor, pressurised water reactor moderator and coolant being different or separated
    • G21C1/12—Heterogeneous reactors, i.e. in which fuel and moderator are separated moderator being highly pressurised, e.g. boiling water reactor, integral super-heat reactor, pressurised water reactor moderator and coolant being different or separated moderator being solid, e.g. Magnox reactor or gas-graphite reactor
    • G—PHYSICS
    • G21—NUCLEAR PHYSICS; NUCLEAR ENGINEERING
    • G21C—NUCLEAR REACTORS
    • G21C11/00—Shielding structurally associated with the reactor
    • G21C11/08—Thermal shields; Thermal linings, i.e. for dissipating heat from gamma radiation which would otherwise heat an outer biological shield ; Thermal insulation
    • G—PHYSICS
    • G21—NUCLEAR PHYSICS; NUCLEAR ENGINEERING
    • G21C—NUCLEAR REACTORS
    • G21C3/00—Reactor fuel elements and their assemblies; Selection of substances for use as reactor fuel elements
    • G21C3/40—Structural combination of fuel element with thermoelectric element for direct production of electric energy from fission heat or with another arrangement for direct production of electric energy, e.g. a thermionic device
    • G—PHYSICS
    • G21—NUCLEAR PHYSICS; NUCLEAR ENGINEERING
    • G21C—NUCLEAR REACTORS
    • G21C5/00—Moderator or core structure; Selection of materials for use as moderator
    • G21C5/12—Moderator or core structure; Selection of materials for use as moderator characterised by composition, e.g. the moderator containing additional substances which ensure improved heat resistance of the moderator
    • 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

  • Engineering & Computer Science (AREA)
  • Physics & Mathematics (AREA)
  • Plasma & Fusion (AREA)
  • General Engineering & Computer Science (AREA)
  • High Energy & Nuclear Physics (AREA)
  • Health & Medical Sciences (AREA)
  • Life Sciences & Earth Sciences (AREA)
  • Biomedical Technology (AREA)
  • General Health & Medical Sciences (AREA)
  • Molecular Biology (AREA)
  • Particle Accelerators (AREA)
  • Structure Of Emergency Protection For Nuclear Reactors (AREA)

Abstract

قلب المفاعل النووي ينتمي إلى مجال الطاقة النووية. يشتمل قلب المفاعل النووي على وحدة واحدة على الأقل من مهدئات النيوترونات صلبة (4) وسائلة. تتكون الوحدة من هيكل (1) وأنبوب حرارة واحد على الأقل وعنصر واحد على الأقل لتوليد الحرارة والعزل الحراري (5). يتكون أنبوب الحرارة على شكل هيكل (2) مزود بفتيلة (6) ويحتوي على حامل حرارة. يتكون عنصر الوقود من الوقود النووي (8) الموجود في منطقة تبخر أنبوب الحرارة حول هيكلها (2) في اتصال حراري به ومرفق في صدفة (3). كسائل التبريد في أنبوب الحرارة الحراري لأنبوب يستخدم المعادن ذات الصهر المنخفض مع درجة غليان عالية ، على سبيل المثال ، الليثيوم والكالسيوم والرصاص والفضة. بين الدرع (3) والهيكل (1) من الوحدة يتم وضع العزل الحراري (5). يتم إجراء ثقب واحد على الأقل في مهدئ النيوترونات الصلب (4) حيث يتم وضع وحدة واحدة على الأقل. تمتلئ المسافة بين هيكل (1) الوحدة والمهدئ النيوترونات الصلب (4) بمهدئ النيوترونات السائل. والنتيجة التقنية هي زيادة كفاءة تحويل الطاقة وتوسيع نطاق قلب المفاعل النووي.
JOP/2019/0307A 2018-08-16 2018-12-25 قلب المفاعل JOP20190307B1 (ar)

Applications Claiming Priority (2)

Application Number Priority Date Filing Date Title
RU2018129925A RU2687288C1 (ru) 2018-08-16 2018-08-16 Активная зона ядерного реактора
PCT/RU2018/000870 WO2020036509A1 (ru) 2018-08-16 2018-12-25 Активная зона ядерного реактора

Publications (2)

Publication Number Publication Date
JOP20190307A1 JOP20190307A1 (ar) 2020-02-16
JOP20190307B1 true JOP20190307B1 (ar) 2023-09-17

Family

ID=66578679

Family Applications (1)

Application Number Title Priority Date Filing Date
JOP/2019/0307A JOP20190307B1 (ar) 2018-08-16 2018-12-25 قلب المفاعل

Country Status (10)

Country Link
US (1) US11476011B2 (ar)
EP (1) EP3839978A4 (ar)
JP (1) JP7014826B2 (ar)
KR (1) KR102422211B1 (ar)
CN (1) CN111066092A (ar)
CA (1) CA3066241C (ar)
EA (1) EA037931B1 (ar)
JO (1) JOP20190307B1 (ar)
RU (1) RU2687288C1 (ar)
WO (1) WO2020036509A1 (ar)

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CN111540489B (zh) * 2020-05-21 2022-09-09 哈尔滨工程大学 一种模块化超临界水冷热管堆系统
CN112102972B (zh) * 2020-08-24 2022-05-13 中国原子能科学研究院 一种用于大功率热管堆的堆芯传热方案
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CN113130097B (zh) * 2021-03-05 2022-04-12 安徽中科超核科技有限公司 一种高效导热的热管反应堆燃料元件
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US20230282380A1 (en) * 2022-03-07 2023-09-07 BWXT Advanced Technologies LLC Fuel bundle with twisted ribbon fuel rodlets for nuclear thermal propulsion applications, structures for manufacture, and methods of manufacture

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Also Published As

Publication number Publication date
EA037931B1 (ru) 2021-06-08
WO2020036509A1 (ru) 2020-02-20
RU2687288C1 (ru) 2019-05-13
CA3066241A1 (en) 2020-02-16
CN111066092A (zh) 2020-04-24
EA201992605A1 (ru) 2020-05-12
JOP20190307A1 (ar) 2020-02-16
EP3839978A1 (en) 2021-06-23
JP7014826B2 (ja) 2022-02-01
BR112019028207A2 (pt) 2021-02-23
JP2021512277A (ja) 2021-05-13
CA3066241C (en) 2023-10-24
KR20200104212A (ko) 2020-09-03
US20210335510A1 (en) 2021-10-28
EP3839978A4 (en) 2022-07-13
US11476011B2 (en) 2022-10-18
KR102422211B1 (ko) 2022-07-18

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