EA201992600A1 - Активная зона ядерного реактора - Google Patents

Активная зона ядерного реактора

Info

Publication number
EA201992600A1
EA201992600A1 EA201992600A EA201992600A EA201992600A1 EA 201992600 A1 EA201992600 A1 EA 201992600A1 EA 201992600 A EA201992600 A EA 201992600A EA 201992600 A EA201992600 A EA 201992600A EA 201992600 A1 EA201992600 A1 EA 201992600A1
Authority
EA
Eurasian Patent Office
Prior art keywords
casing
module
liquid
heat pipe
core
Prior art date
Application number
EA201992600A
Other languages
English (en)
Other versions
EA036719B1 (ru
Inventor
Николай Иванович ЛОГИНОВ
Виктор Викторович ЛИТВИНОВ
Алексей Дмитриевич КРОТОВ
Original Assignee
Акционерное Общество "Государственный Научный Центр Российской Федерации - Физико-Энергетический Институт Имени А.И. Лейпунского" (Ао "Гнц Рф - Фэи")
Акционерное Общество "Наука И Инновации" (Ао "Наука И Инновации")
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 Акционерное Общество "Государственный Научный Центр Российской Федерации - Физико-Энергетический Институт Имени А.И. Лейпунского" (Ао "Гнц Рф - Фэи"), Акционерное Общество "Наука И Инновации" (Ао "Наука И Инновации") filed Critical Акционерное Общество "Государственный Научный Центр Российской Федерации - Физико-Энергетический Институт Имени А.И. Лейпунского" (Ао "Гнц Рф - Фэи")
Publication of EA201992600A1 publication Critical patent/EA201992600A1/ru
Publication of EA036719B1 publication Critical patent/EA036719B1/ru

Links

Classifications

    • 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
    • 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
    • G21C3/00—Reactor fuel elements and their assemblies; Selection of substances for use as reactor fuel elements
    • G21C3/30—Assemblies of a number of fuel elements in the form of a rigid unit
    • G21C3/32—Bundles of parallel pin-, rod-, or tube-shaped fuel elements
    • G21C3/322—Means to influence the coolant flow through or around the bundles
    • 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
    • G21C5/02—Details
    • 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

  • Physics & Mathematics (AREA)
  • Engineering & Computer Science (AREA)
  • Plasma & Fusion (AREA)
  • General Engineering & Computer Science (AREA)
  • High Energy & Nuclear Physics (AREA)
  • Particle Accelerators (AREA)
  • Structure Of Emergency Protection For Nuclear Reactors (AREA)
  • Organic Low-Molecular-Weight Compounds And Preparation Thereof (AREA)
  • Monitoring And Testing Of Nuclear Reactors (AREA)

Abstract

Активная зона ядерного реактора относится к области атомной энергетики. Активная зона ядерного реактора включает по меньшей мере один модуль, твёрдый (5) и жидкий замедлители нейтронов. Модуль содержит корпус (2), по меньшей мере одну тепловую трубу, по меньшей мере один тепловыделяющий элемент, кожух (1) и теплоизоляцию (6). Тепловая труба выполнена из корпуса (3), фитиля (7) и содержит испаряющийся теплоноситель. Тепловыделяющий элемент состоит из оболочки (4) и ядерного топлива (9). Зона испарения тепловой трубы и тепловыделяющие элементы заключены в кожух (1), заполненный жидким теплоносителем. В качестве теплоносителя тепловой трубы и жидкого теплоносителя в кожухе (1) используют жидкие металлы с высокой температурой кипения, например литий, кальций, свинец, серебро. В пространстве между кожухом (1) и корпусом модуля (2) помещена теплоизоляция (6). Твёрдый замедлитель нейтронов (5) имеет по меньшей мере одно отверстие, в котором размещён по меньшей мере один модуль. Пространство между твёрдым замедлителем нейтронов (5) и модулем заполнено жидким замедлителем нейтронов. Технический результат - повышение коэффициента полезного действия реакторных установок и расширение области применения активной зоны.
EA201992600A 2018-04-13 2018-12-25 Активная зона ядерного реактора EA036719B1 (ru)

Applications Claiming Priority (2)

Application Number Priority Date Filing Date Title
RU2018113680A RU2680250C1 (ru) 2018-04-13 2018-04-13 Активная зона ядерного реактора
PCT/RU2018/000869 WO2019199200A1 (ru) 2018-04-13 2018-12-25 Активная зона ядерного реактора

Publications (2)

Publication Number Publication Date
EA201992600A1 true EA201992600A1 (ru) 2020-03-02
EA036719B1 EA036719B1 (ru) 2020-12-11

Family

ID=65442573

Family Applications (1)

Application Number Title Priority Date Filing Date
EA201992600A EA036719B1 (ru) 2018-04-13 2018-12-25 Активная зона ядерного реактора

Country Status (14)

Country Link
US (1) US11469005B2 (ru)
EP (1) EP3780004B8 (ru)
JP (1) JP6972189B2 (ru)
KR (1) KR102428565B1 (ru)
CN (1) CN110945600B (ru)
BR (1) BR112019028262A2 (ru)
CA (1) CA3068592A1 (ru)
EA (1) EA036719B1 (ru)
FI (1) FI3780004T3 (ru)
HU (1) HUE062416T2 (ru)
JO (1) JOP20190299B1 (ru)
MY (1) MY198014A (ru)
RU (1) RU2680250C1 (ru)
WO (1) WO2019199200A1 (ru)

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CN111081398A (zh) * 2019-12-31 2020-04-28 中国核动力研究设计院 一种无间隙固态传热的一体化快谱堆芯结构
CN111478624B (zh) * 2020-04-09 2021-07-16 中国科学院上海应用物理研究所 热端座、温差发电***、液态堆及其运行方法和应用
CN111739666B (zh) * 2020-06-23 2021-12-31 上海交通大学 一种用于空间探索的行波堆
CN111951986B (zh) * 2020-08-20 2021-04-30 大连理工大学 一种核燃料棒与热压转换传热器件的嵌套结构
CN112117016B (zh) * 2020-08-24 2022-07-01 中国原子能科学研究院 一种热管堆堆芯传热***
CN112355311B (zh) * 2020-10-21 2022-08-02 中国科学院合肥物质科学研究院 一种钨基金属陶瓷核燃料芯块及其制备方法
CN112865606B (zh) 2020-12-08 2022-07-22 上海核工程研究设计院有限公司 一种碱金属反应堆电源

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Also Published As

Publication number Publication date
JOP20190299A1 (ar) 2019-12-30
FI3780004T3 (fi) 2023-06-21
WO2019199200A1 (ru) 2019-10-17
US11469005B2 (en) 2022-10-11
US20210027900A1 (en) 2021-01-28
JOP20190299B1 (ar) 2023-09-17
EP3780004B1 (en) 2023-04-12
CN110945600B (zh) 2024-02-02
JP6972189B2 (ja) 2021-11-24
BR112019028262A2 (pt) 2020-08-04
JP2020530898A (ja) 2020-10-29
KR20200103531A (ko) 2020-09-02
MY198014A (en) 2023-07-26
KR102428565B1 (ko) 2022-08-03
CN110945600A (zh) 2020-03-31
EP3780004A4 (en) 2022-01-26
EP3780004B8 (en) 2023-06-21
CA3068592A1 (en) 2019-10-17
RU2680250C1 (ru) 2019-02-19
HUE062416T2 (hu) 2023-11-28
EA036719B1 (ru) 2020-12-11
EP3780004A1 (en) 2021-02-17

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Legal Events

Date Code Title Description
MM4A Lapse of a eurasian patent due to non-payment of renewal fees within the time limit in the following designated state(s)

Designated state(s): AZ KG TJ TM RU