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)

Families Citing this family (9)

* Cited by examiner, † Cited by third party
Publication number Priority date Publication date Assignee Title
CN111081393B (zh) * 2019-12-31 2022-06-28 中国核动力研究设计院 一种采用热管和燃料棒的一体化固体堆芯结构
WO2021178953A2 (en) * 2020-03-06 2021-09-10 Oklo Inc. Fuel, heat exchanger, and instrumentation for nuclear reactors
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
US11955249B2 (en) * 2020-10-29 2024-04-09 Westinghouse Electric Company Llc Heat pipe having a wick between concentric inner and outer housings, for use in heat removal from a nuclear reactor core
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
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
CN113362971B (zh) * 2021-05-21 2022-10-28 西安交通大学 一种用于静态转换的紧凑型热管堆堆芯结构
US20230282374A1 (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

Family Cites Families (18)

* Cited by examiner, † Cited by third party
Publication number Priority date Publication date Assignee Title
NL249638A (ar) * 1959-03-21
DE1274750B (de) * 1966-05-13 1968-08-08 Bbc Brown Boveri & Cie Thermionisches Konverter-Brennelement
US4506183A (en) * 1980-11-30 1985-03-19 The United States Of America As Represented By The Administrator Of The National Aeronautics And Space Administration High thermal power density heat transfer apparatus providing electrical isolation at high temperature using heat pipes
US5408510A (en) * 1994-04-11 1995-04-18 The Babcock & Wilcox Company Thermionic nuclear reactor with flux shielded components
US6037697A (en) * 1999-01-18 2000-03-14 General Atomics Thermionic converter and method of making same
RU2165656C1 (ru) * 1999-08-26 2001-04-20 Открытое акционерное общество "Ракетно-космическая корпорация "Энергия" им. С.П. Королева" Термоэмиссионный реактор-преобразователь
RU2187156C2 (ru) * 2000-06-29 2002-08-10 Государственное унитарное предприятие "Государственный научный центр Российской Федерации - Физико-энергетический институт им. академика А.И.Лейпунского" Термоэмиссионный электрогенерирующий модуль для активной зоны ядерного реактора с вынесенной термоэмиссионной системой преобразования тепловой энергии в электрическую (варианты)
DE10123690A1 (de) * 2001-05-15 2002-12-05 Framatome Anp Gmbh Verfahren zum Schutz der Bauteile des Primärsystems eines Siedewasserreaktors insbesondere vor Spannungsrisskorrosion
RU2328042C2 (ru) * 2006-06-14 2008-06-27 ФГУП Опытное конструкторское бюро "ГИДРОПРЕСС" Активная зона ядерного реактора
US8987579B2 (en) * 2011-05-05 2015-03-24 Aerojet Rocketdyne Of De, Inc. Power converter
US10643756B2 (en) * 2013-04-25 2020-05-05 Triad National Security, Llc Mobile heat pipe cooled fast reactor system
US10276271B2 (en) * 2013-04-25 2019-04-30 Triad National Security, LLC. Electric fission reactor for space applications
RU2595639C2 (ru) * 2014-12-04 2016-08-27 Акционерное общество "Научно-исследовательский и проектно-конструкторский институт энергетических технологий "АТОМПРОЕКТ" ("АО "АТОМПРОЕКТ") Система пассивного отвода тепла из внутреннего объема защитной оболочки
CN104766636B (zh) * 2015-04-20 2017-07-25 中国科学技术大学 一种核燃料棒与中心冷却热管的嵌套一体化结构
JP2017181445A (ja) 2016-03-31 2017-10-05 株式会社東芝 可搬式原子炉およびその炉心
EP3513409A4 (en) 2016-09-13 2020-03-04 Westinghouse Electric Company Llc FAST REACTOR WITH MOLTEN SALT IN HEAT PIPES WITH STAGNANT LIQUID C UR
US10559389B2 (en) * 2017-02-06 2020-02-11 Battell Energy Alliance, LLC Modular nuclear reactors including fuel elements and heat pipes extending through grid plates, and methods of forming the modular nuclear reactors
RU2660942C1 (ru) * 2017-12-05 2018-07-11 Акционерное общество "Государственный научный центр Российской Федерации - Физико-энергетический институт имени А.И. Лейпунского" Активная зона ядерного реактора

Also Published As

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

Similar Documents

Publication Publication Date Title
JOP20190307B1 (ar) قلب المفاعل
JOP20190299B1 (ar) قلب المفاعل
Jeong et al. Hybrid heat pipe based passive in-core cooling system for advanced nuclear power plant
CN104766636B (zh) 一种核燃料棒与中心冷却热管的嵌套一体化结构
CA3156686A1 (en) LOW-POWER, FAST-SPECTRUM MOLTEN FUEL REACTOR
WO2018204857A3 (en) Gas-cooled pressure tube reactor
KR20190086887A (ko) 토륨 연료 기반 우주원자로 노심 및 이를 구비한 원자로
Albzeirat et al. Applications of nano-fluid in nuclear power plants within a future vision
CN104052333A (zh) 一种利用堆芯熔融物衰变热发电的系统
Wei et al. Neutronic/thermal‐hydraulic design features of an improved lead‐bismuth cooled small modular fast reactor
Dudek et al. Thermodynamic analysis of power generation cycles with high-temperature gas-cooled nuclear reactor and additional coolant heating up to 1600 C
Bammert A general review of closed-cycle gas turbines using fossil, nuclear and solar energy
US20190385758A1 (en) Combination reactor gamma radiation power harvesting reactor power distribution measurement, and support to coolant freezing protection system for liquid metal and molten salt-cooled reactor systems
RU2014141718A (ru) Космическая двухрежимная ядерно-энергетическая установка транспортно-энергетического модуля
Brey Development history of the gas turbine modular high temperature reactor
CN104599730A (zh) 一种压水堆核电发电机构
Sink Very High Temperature Reactors
CN102842345A (zh) 锝—99作为可燃毒物元件的应用
Hoang et al. Conceptual design of a small-pressurized water reactor using the AP1000 fuel assembly design
Li et al. Preliminary design and neutronics analysis for a medium temperature heat pipe cooled reactor
JP2016176719A (ja) 正方形沸騰水型原子炉
Takahashi et al. Design concepts of LFRs and related studies in CRINES of Tokyo Tech
Surayev et al. The concept of an effective NPP with a gas-cooled thermal neutron reactor
Cleve Breeding of Fissile Uranium 233 Using Thorium 232 with Pebble Fuel Elements
Hartanto et al. Lead-based Radial Reflectors for Sodium-cooled Fast Reactor