JP2021512277A - 原子炉の炉心 - Google Patents
原子炉の炉心 Download PDFInfo
- Publication number
- JP2021512277A JP2021512277A JP2019572823A JP2019572823A JP2021512277A JP 2021512277 A JP2021512277 A JP 2021512277A JP 2019572823 A JP2019572823 A JP 2019572823A JP 2019572823 A JP2019572823 A JP 2019572823A JP 2021512277 A JP2021512277 A JP 2021512277A
- Authority
- JP
- Japan
- Prior art keywords
- core
- heat pipe
- neutron moderator
- module
- casing
- Prior art date
- Legal status (The legal status 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 status listed.)
- Granted
Links
- 239000000446 fuel Substances 0.000 claims abstract description 33
- 239000007787 solid Substances 0.000 claims abstract description 28
- 239000007788 liquid Substances 0.000 claims abstract description 26
- 239000002826 coolant Substances 0.000 claims abstract description 22
- 239000003758 nuclear fuel Substances 0.000 claims abstract description 14
- 238000001704 evaporation Methods 0.000 claims abstract description 7
- 238000009835 boiling Methods 0.000 claims abstract description 6
- 230000008020 evaporation Effects 0.000 claims abstract description 6
- WHXSMMKQMYFTQS-UHFFFAOYSA-N Lithium Chemical compound [Li] WHXSMMKQMYFTQS-UHFFFAOYSA-N 0.000 claims abstract description 5
- 229910052744 lithium Inorganic materials 0.000 claims abstract description 5
- 229910052751 metal Inorganic materials 0.000 claims abstract description 5
- 239000002184 metal Substances 0.000 claims abstract description 5
- OYPRJOBELJOOCE-UHFFFAOYSA-N Calcium Chemical compound [Ca] OYPRJOBELJOOCE-UHFFFAOYSA-N 0.000 claims abstract description 4
- 229910052791 calcium Inorganic materials 0.000 claims abstract description 4
- 239000011575 calcium Substances 0.000 claims abstract description 4
- 239000011133 lead Substances 0.000 claims abstract description 4
- 229910052709 silver Inorganic materials 0.000 claims abstract description 4
- 239000004332 silver Substances 0.000 claims abstract description 4
- XLYOFNOQVPJJNP-UHFFFAOYSA-N water Substances O XLYOFNOQVPJJNP-UHFFFAOYSA-N 0.000 claims description 6
- LFQSCWFLJHTTHZ-UHFFFAOYSA-N Ethanol Chemical compound CCO LFQSCWFLJHTTHZ-UHFFFAOYSA-N 0.000 claims description 4
- 239000011261 inert gas Substances 0.000 claims description 4
- 229910052724 xenon Inorganic materials 0.000 claims description 3
- FHNFHKCVQCLJFQ-UHFFFAOYSA-N xenon atom Chemical compound [Xe] FHNFHKCVQCLJFQ-UHFFFAOYSA-N 0.000 claims description 3
- 239000011810 insulating material Substances 0.000 abstract description 6
- 238000009413 insulation Methods 0.000 abstract description 4
- 238000002844 melting Methods 0.000 abstract description 4
- 230000008018 melting Effects 0.000 abstract description 4
- 238000010586 diagram Methods 0.000 abstract 1
- 150000002739 metals Chemical class 0.000 abstract 1
- ZOKXTWBITQBERF-UHFFFAOYSA-N Molybdenum Chemical compound [Mo] ZOKXTWBITQBERF-UHFFFAOYSA-N 0.000 description 7
- 239000000463 material Substances 0.000 description 7
- 229910052750 molybdenum Inorganic materials 0.000 description 7
- 239000011733 molybdenum Substances 0.000 description 7
- 239000000243 solution Substances 0.000 description 6
- 238000006243 chemical reaction Methods 0.000 description 5
- 239000007789 gas Substances 0.000 description 5
- 229910001093 Zr alloy Inorganic materials 0.000 description 3
- 229910052790 beryllium Inorganic materials 0.000 description 3
- ATBAMAFKBVZNFJ-UHFFFAOYSA-N beryllium atom Chemical compound [Be] ATBAMAFKBVZNFJ-UHFFFAOYSA-N 0.000 description 3
- 230000004992 fission Effects 0.000 description 3
- 239000008188 pellet Substances 0.000 description 3
- 238000001816 cooling Methods 0.000 description 2
- 239000004173 sunset yellow FCF Substances 0.000 description 2
- 229910052778 Plutonium Inorganic materials 0.000 description 1
- 229910052770 Uranium Inorganic materials 0.000 description 1
- QCWXUUIWCKQGHC-UHFFFAOYSA-N Zirconium Chemical compound [Zr] QCWXUUIWCKQGHC-UHFFFAOYSA-N 0.000 description 1
- 239000007864 aqueous solution Substances 0.000 description 1
- MVXWAZXVYXTENN-UHFFFAOYSA-N azanylidyneuranium Chemical compound [U]#N MVXWAZXVYXTENN-UHFFFAOYSA-N 0.000 description 1
- 239000003638 chemical reducing agent Substances 0.000 description 1
- 238000005260 corrosion Methods 0.000 description 1
- 230000007797 corrosion Effects 0.000 description 1
- 239000011888 foil Substances 0.000 description 1
- 239000012774 insulation material Substances 0.000 description 1
- 150000001247 metal acetylides Chemical class 0.000 description 1
- 238000000034 method Methods 0.000 description 1
- 150000004767 nitrides Chemical class 0.000 description 1
- OOAWCECZEHPMBX-UHFFFAOYSA-N oxygen(2-);uranium(4+) Chemical compound [O-2].[O-2].[U+4] OOAWCECZEHPMBX-UHFFFAOYSA-N 0.000 description 1
- OYEHPCDNVJXUIW-UHFFFAOYSA-N plutonium atom Chemical compound [Pu] OYEHPCDNVJXUIW-UHFFFAOYSA-N 0.000 description 1
- 239000011819 refractory material Substances 0.000 description 1
- 239000003870 refractory metal Substances 0.000 description 1
- 238000001228 spectrum Methods 0.000 description 1
- FCTBKIHDJGHPPO-UHFFFAOYSA-N uranium dioxide Inorganic materials O=[U]=O FCTBKIHDJGHPPO-UHFFFAOYSA-N 0.000 description 1
- JFALSRSLKYAFGM-UHFFFAOYSA-N uranium(0) Chemical compound [U] JFALSRSLKYAFGM-UHFFFAOYSA-N 0.000 description 1
Images
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
- 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
- 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
- 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
Description
実施の形態における一の特定の場合では、炉心モジュールのケーシング(モジュールケーシング)1内が真空にされる。また、別の特定の場合には、ケーシング1内は、低熱伝導率である不活性ガス、例えば、キセノンで満たされている。
固体中性子減速材4は、直径760mm、全高約700mm、直径40mmの217個の穴を持ついくつかのベリリウムディスクで構成されている。ベリリウムディスクは、ジルコニウム合金E110製のシェル7で完全に囲まれている。
2 ヒートパイプのケーシング
3 燃料要素の容器
4 固体中性子減速材
5 断熱材
6 芯
7 固体中性子減速材の外側シェル
8 核燃料
Claims (6)
- 原子炉の炉心であって、
1つのヒートパイプと少なくとも1つの燃料要素とを含むモジュールを少なくとも1つ備え、
前記ヒートパイプは、ヒートパイプケーシングと、芯と、冷却材とを含み、
前記燃料要素は、核燃料と容器とを含み、
前記炉心は、内部に前記少なくとも1つのモジュールが配置されるための少なくとも1つの穴を有する固体中性子減速材固体を炉心ケーシング内に配してなり、
前記ヒートパイプがモジュールケーシング内に配され、
燃料要素がヒートパイプの蒸発領域の周囲に、ヒートパイプケーシングと熱接触するような状態で配置されて、容器内に収納されており、
前記モジュールケーシングと前記固体中性子減速材との間の隙間は、液体中性子減速材で満たされている
ことを特徴とする原子炉の炉心。 - 前記モジュールケーシング内が、真空にされていることを特徴とする請求項1に記載の原子炉の炉心。
- 前記モジュールケーシング内が、熱伝導率の低い不活性ガス、例えば、キセノンで満たされていることを特徴とする請求項1に記載の原子炉の炉心。
- 例えば、リチウム、カルシウム、鉛、銀などの高沸点で低融点の金属が、前記ヒートパイプの冷却材として使用されることを特徴とする請求項1に記載の原子炉の炉心。
- 水が、液体中性子減速材として使用されることを特徴とする請求項1に記載の原子炉の炉心。
- アルコール液など、少なくともマイナス40℃までは凍結しない液体が、液体中性子減速材として使用されることを特徴とする請求項1に記載の原子炉の炉心。
Applications Claiming Priority (3)
Application Number | Priority Date | Filing Date | Title |
---|---|---|---|
RU2018129925 | 2018-08-16 | ||
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 |
---|---|
JP2021512277A true JP2021512277A (ja) | 2021-05-13 |
JP7014826B2 JP7014826B2 (ja) | 2022-02-01 |
Family
ID=66578679
Family Applications (1)
Application Number | Title | Priority Date | Filing Date |
---|---|---|---|
JP2019572823A Active JP7014826B2 (ja) | 2018-08-16 | 2018-12-25 | 原子炉の炉心 |
Country Status (10)
Country | Link |
---|---|
US (1) | US11476011B2 (ja) |
EP (1) | EP3839978A4 (ja) |
JP (1) | JP7014826B2 (ja) |
KR (1) | KR102422211B1 (ja) |
CN (1) | CN111066092A (ja) |
CA (1) | CA3066241C (ja) |
EA (1) | EA037931B1 (ja) |
JO (1) | JOP20190307B1 (ja) |
RU (1) | RU2687288C1 (ja) |
WO (1) | WO2020036509A1 (ja) |
Families Citing this family (9)
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 |
US11735326B2 (en) * | 2020-03-06 | 2023-08-22 | Oklo Inc. | System having heat pipe passing through annulus of nuclear fuel element |
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 |
WO2023172563A2 (en) * | 2022-03-07 | 2023-09-14 | BWXT Advanced Technologies LLC | Fuel bundle with twisted ribbon fuel rodlets for nuclear thermal propulsion applications, structures for manufacture, and methods of manufacture |
Citations (3)
Publication number | Priority date | Publication date | Assignee | Title |
---|---|---|---|---|
US20160027536A1 (en) * | 2013-04-25 | 2016-01-28 | Los Alamos National Security , LLC | Mobile heat pipe cooled fast reactor system |
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 |
US20180075931A1 (en) * | 2016-09-13 | 2018-03-15 | Westinghouse Electric Company, Llc | Heat pipe molten salt fast reactor with stagnant liquid core |
Family Cites Families (15)
Publication number | Priority date | Publication date | Assignee | Title |
---|---|---|---|---|
NL263017A (ja) * | 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 |
WO2014204543A1 (en) * | 2013-04-25 | 2014-12-24 | Los Alamos 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 |
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 |
-
2018
- 2018-08-16 RU RU2018129925A patent/RU2687288C1/ru active
- 2018-12-25 EA EA201992605A patent/EA037931B1/ru unknown
- 2018-12-25 CA CA3066241A patent/CA3066241C/en active Active
- 2018-12-25 EP EP18922094.0A patent/EP3839978A4/en active Pending
- 2018-12-25 CN CN201880043547.6A patent/CN111066092A/zh active Pending
- 2018-12-25 JP JP2019572823A patent/JP7014826B2/ja active Active
- 2018-12-25 WO PCT/RU2018/000870 patent/WO2020036509A1/ru unknown
- 2018-12-25 JO JOP/2019/0307A patent/JOP20190307B1/ar active
- 2018-12-25 KR KR1020197038617A patent/KR102422211B1/ko active IP Right Grant
- 2018-12-25 US US16/627,738 patent/US11476011B2/en active Active
Patent Citations (3)
Publication number | Priority date | Publication date | Assignee | Title |
---|---|---|---|---|
US20160027536A1 (en) * | 2013-04-25 | 2016-01-28 | Los Alamos National Security , LLC | Mobile heat pipe cooled fast reactor system |
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 |
US20180075931A1 (en) * | 2016-09-13 | 2018-03-15 | Westinghouse Electric Company, Llc | Heat pipe molten salt fast reactor with stagnant liquid core |
Also Published As
Publication number | Publication date |
---|---|
US11476011B2 (en) | 2022-10-18 |
WO2020036509A1 (ru) | 2020-02-20 |
CA3066241C (en) | 2023-10-24 |
EA037931B1 (ru) | 2021-06-08 |
KR20200104212A (ko) | 2020-09-03 |
JOP20190307B1 (ar) | 2023-09-17 |
EA201992605A1 (ru) | 2020-05-12 |
RU2687288C1 (ru) | 2019-05-13 |
US20210335510A1 (en) | 2021-10-28 |
EP3839978A1 (en) | 2021-06-23 |
JP7014826B2 (ja) | 2022-02-01 |
BR112019028207A2 (pt) | 2021-02-23 |
JOP20190307A1 (ar) | 2020-02-16 |
EP3839978A4 (en) | 2022-07-13 |
CN111066092A (zh) | 2020-04-24 |
KR102422211B1 (ko) | 2022-07-18 |
CA3066241A1 (en) | 2020-02-16 |
Similar Documents
Publication | Publication Date | Title |
---|---|---|
JP7014826B2 (ja) | 原子炉の炉心 | |
RU2680250C1 (ru) | Активная зона ядерного реактора | |
US10692612B2 (en) | Nuclear reactor and a method of heat transfer from a core | |
RU2159479C2 (ru) | Термоэмиссионный ядерный реактор | |
JP2022552608A (ja) | 液体金属合金の燃料及び/又は減速材を有する原子炉 | |
JP2021092566A (ja) | 完全に受動的な残留力除去(dhr)システムを組み込んだ液体金属冷却原子炉 | |
RU2660942C1 (ru) | Активная зона ядерного реактора | |
JP2018009890A (ja) | 核融合炉ブランケットサブユニットおよびその製造方法ならびに核融合炉ブランケット | |
TWI803036B (zh) | 用於自核反應器核心移除熱量之裝置、系統及方法 | |
JP2021179313A (ja) | 原子炉および原子炉の除熱方法 | |
BR112019028207B1 (pt) | Área ativa de um reator nuclear | |
Fratoni et al. | Preliminary feasibility study of the heat-pipe ENHS Reactor | |
CN115424743A (zh) | 一种用于卧式堆的非能动热量导出系统 |
Legal Events
Date | Code | Title | Description |
---|---|---|---|
A621 | Written request for application examination |
Free format text: JAPANESE INTERMEDIATE CODE: A621 Effective date: 20200722 |
|
A131 | Notification of reasons for refusal |
Free format text: JAPANESE INTERMEDIATE CODE: A131 Effective date: 20210831 |
|
A521 | Request for written amendment filed |
Free format text: JAPANESE INTERMEDIATE CODE: A523 Effective date: 20211130 |
|
TRDD | Decision of grant or rejection written | ||
A01 | Written decision to grant a patent or to grant a registration (utility model) |
Free format text: JAPANESE INTERMEDIATE CODE: A01 Effective date: 20211221 |
|
A61 | First payment of annual fees (during grant procedure) |
Free format text: JAPANESE INTERMEDIATE CODE: A61 Effective date: 20220120 |