JP7661482B2 - 原子炉用カートリッジ炉心バレル - Google Patents
原子炉用カートリッジ炉心バレル Download PDFInfo
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- JP7661482B2 JP7661482B2 JP2023511582A JP2023511582A JP7661482B2 JP 7661482 B2 JP7661482 B2 JP 7661482B2 JP 2023511582 A JP2023511582 A JP 2023511582A JP 2023511582 A JP2023511582 A JP 2023511582A JP 7661482 B2 JP7661482 B2 JP 7661482B2
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- G—PHYSICS
- G21—NUCLEAR PHYSICS; NUCLEAR ENGINEERING
- G21C—NUCLEAR REACTORS
- G21C21/00—Apparatus or processes specially adapted to the manufacture of reactors or parts thereof
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- F—MECHANICAL ENGINEERING; LIGHTING; HEATING; WEAPONS; BLASTING
- F04—POSITIVE - DISPLACEMENT MACHINES FOR LIQUIDS; PUMPS FOR LIQUIDS OR ELASTIC FLUIDS
- F04B—POSITIVE-DISPLACEMENT MACHINES FOR LIQUIDS; PUMPS
- F04B17/00—Pumps characterised by combination with, or adaptation to, specific driving engines or motors
- F04B17/03—Pumps characterised by combination with, or adaptation to, specific driving engines or motors driven by electric motors
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- F—MECHANICAL ENGINEERING; LIGHTING; HEATING; WEAPONS; BLASTING
- F04—POSITIVE - DISPLACEMENT MACHINES FOR LIQUIDS; PUMPS FOR LIQUIDS OR ELASTIC FLUIDS
- F04B—POSITIVE-DISPLACEMENT MACHINES FOR LIQUIDS; PUMPS
- F04B19/00—Machines or pumps having pertinent characteristics not provided for in, or of interest apart from, groups F04B1/00 - F04B17/00
- F04B19/04—Pumps for special use
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- G—PHYSICS
- G21—NUCLEAR PHYSICS; NUCLEAR ENGINEERING
- G21C—NUCLEAR REACTORS
- G21C1/00—Reactor types
- G21C1/02—Fast fission reactors, i.e. reactors not using a moderator ; Metal cooled reactors; Fast breeders
- G21C1/028—Fast fission reactors, i.e. reactors not using a moderator ; Metal cooled reactors; Fast breeders cooled by a pressurised coolant
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- G—PHYSICS
- G21—NUCLEAR PHYSICS; NUCLEAR ENGINEERING
- G21C—NUCLEAR REACTORS
- G21C1/00—Reactor types
- G21C1/02—Fast fission reactors, i.e. reactors not using a moderator ; Metal cooled reactors; Fast breeders
- G21C1/03—Fast fission reactors, i.e. reactors not using a moderator ; Metal cooled reactors; Fast breeders cooled by a coolant not essentially pressurised, e.g. pool-type reactors
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- 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
- G21C1/14—Heterogeneous reactors, i.e. in which fuel and moderator are separated moderator being substantially not pressurised, e.g. swimming-pool reactor
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- G—PHYSICS
- G21—NUCLEAR PHYSICS; NUCLEAR ENGINEERING
- G21C—NUCLEAR REACTORS
- G21C13/00—Pressure vessels; Containment vessels; Containment in general
- G21C13/02—Details
- G21C13/024—Supporting constructions for pressure vessels or containment vessels
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- G—PHYSICS
- G21—NUCLEAR PHYSICS; NUCLEAR ENGINEERING
- G21C—NUCLEAR REACTORS
- G21C13/00—Pressure vessels; Containment vessels; Containment in general
- G21C13/02—Details
- G21C13/04—Arrangements for expansion and contraction
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- 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
- G21C15/02—Arrangements or disposition of passages in which heat is transferred to the coolant; Coolant flow control devices
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- 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
- G21C15/243—Promoting flow of the coolant for liquids
- G21C15/247—Promoting flow of the coolant for liquids for liquid metals
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- 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
- G21C15/26—Promoting flow of the coolant by convection, e.g. using chimneys, using divergent channels
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- 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"
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- 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
- G21C5/10—Means for supporting the complete structure
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- H—ELECTRICITY
- H02—GENERATION; CONVERSION OR DISTRIBUTION OF ELECTRIC POWER
- H02K—DYNAMO-ELECTRIC MACHINES
- H02K44/00—Machines in which the dynamo-electric interaction between a plasma or flow of conductive liquid or of fluid-borne conductive or magnetic particles and a coil system or magnetic field converts energy of mass flow into electrical energy or vice versa
- H02K44/02—Electrodynamic pumps
- H02K44/06—Induction pumps
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- G—PHYSICS
- G21—NUCLEAR PHYSICS; NUCLEAR ENGINEERING
- G21C—NUCLEAR REACTORS
- G21C1/00—Reactor types
- G21C1/32—Integral reactors, i.e. reactors wherein parts functionally associated with the reactor but not essential to the reaction, e.g. heat exchangers, are disposed inside the enclosure with the core
- G21C1/326—Integral reactors, i.e. reactors wherein parts functionally associated with the reactor but not essential to the reaction, e.g. heat exchangers, are disposed inside the enclosure with the core wherein the heat exchanger is disposed next to or beside the core
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- 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
- G21C15/02—Arrangements or disposition of passages in which heat is transferred to the coolant; Coolant flow control devices
- G21C15/12—Arrangements or disposition of passages in which heat is transferred to the coolant; Coolant flow control devices from pressure vessel; from containment vessel
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- 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
- G21C15/182—Emergency cooling arrangements; Removing shut-down heat comprising powered means, e.g. pumps
- G21C15/185—Emergency cooling arrangements; Removing shut-down heat comprising powered means, e.g. pumps using energy stored in reactor system
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- 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
- G21C3/33—Supporting or hanging of elements in the bundle; Means forming part of the bundle for inserting it into, or removing it from, the core; Means for coupling adjacent bundles
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- 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
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- 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
- G21C9/04—Means for suppressing fires ; Earthquake protection
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- 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
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- 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
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- Engineering & Computer Science (AREA)
- Physics & Mathematics (AREA)
- General Engineering & Computer Science (AREA)
- High Energy & Nuclear Physics (AREA)
- Plasma & Fusion (AREA)
- Mechanical Engineering (AREA)
- Power Engineering (AREA)
- Chemical & Material Sciences (AREA)
- Chemical Kinetics & Catalysis (AREA)
- Manufacturing & Machinery (AREA)
- Structures Of Non-Positive Displacement Pumps (AREA)
- Monitoring And Testing Of Nuclear Reactors (AREA)
- Structure Of Emergency Protection For Nuclear Reactors (AREA)
Description
本願は、2021年2月1日に出願された「CARTRIDGE CORE BARREL FOR NUCLEAR REACTOR」という名称の米国特許出願第17/164,820号の利益を主張し、それは、2020年8月17日に出願された「CARTRIDGE CORE BARREL FOR NUCLEAR REACTOR」という名称の仮特許出願第63/066,785号の優先権を主張する。その内容全体は、参照によって本明細書に援用される。
ほとんどの原子炉は、炉心を有し、当該炉心内では、燃料要素および制御要素が様々な相互に関連する配置で支持され、これにより臨界反応度をサポートして原子炉の出力を制御する。冷却材は、典型的には燃料要素と制御要素との間の通路を通って押し出され、これにより核分裂燃料要素によって生成された熱は、有益な目的に使用される熱交換器に伝達される。
いくつかの実施形態によれば、原子炉容器が原子炉ヘッドから吊り下げられる原子炉配置が説明される。しかしながら、炉心の重量は、原子炉ヘッドによって支持されなくてもよく、むしろ、原子炉容器の外部に位置し、地面によって支持される支持構造体に直接的に伝達されてもよい。いくつかの例では、炉心が原子炉容器ヘッドから吊り下げられたカートリッジによって支持され、したがって、炉心および制御要素の両方の荷重経路は共通の支持構造体に結合される。これにより、炉心と制御要素との間の潜在的な相対運動は低減される。
図1は、いくつかの実施形態に係る、原子炉支持構造体の模式図である;
図2は、いくつかの実施形態に係る、炉心-容器インターフェースのための下方炉心支持構造体を示す;
図3は、いくつかの実施形態に係る、炉心-容器インターフェースのための下方炉心支持構造体を示す;
図4は、いくつかの実施形態に係る、炉心-容器インターフェースのための吊り下げ張力スカートを有する下方炉心支持構造体を示す;
図5は、いくつかの実施形態に係る、複数のリブを有する下方炉心支持構造体を示す;
図6は、いくつかの実施形態に係る、原子炉容器から独立した下方炉心支持構造体を示す;
図7は、いくつかの実施形態に係る、底部支持型の容器構成における下方炉心支持構造体を示す;
図8は、いくつかの実施形態に係る、原子炉ヘッドから吊り下げられるように構成された炉心支持構造体を示す;
図9は、いくつかの実施形態に係る、炉心支持体を制御棒支持体と結合するためにカートリッジを利用する炉心支持構造体を示す;
図10は、いくつかの実施形態に係る、下方炉心支持構造体および原子炉容器を介した荷重経路を示す;
図11は、いくつかの実施形態に係る、原子炉容器から独立して炉心を支持するカートリッジ炉心支持構造体を示す;
図12は、いくつかの実施形態に係る、カートリッジモジュールを示す。
本開示は、概して、(場合によっては原子炉容器の円筒形支持体に遷移する円錐形支持体である)原子炉容器の支持体、または原子炉炉心の支持体、などの下方炉心支持体のための装置に関する。場合によっては、円錐形支持セクション内の複数の垂直リブにより、追加の剛性(stiffness)、剛性(rigidity)、および支持が提供される。
Claims (8)
- 制御要素を保持する制御要素支持構造体を含む原子炉容器ヘッドと、
上部および下部を有し、内部で炉心を支持する支持円筒と、
前記上部におけるマウントであって、前記制御要素支持構造体と係合し、当該原子炉容器ヘッドから前記支持円筒の重量を支持するマウントと、を備え、
前記支持円筒は、前記制御要素支持構造体から吊り下げられている、原子炉炉心支持システム。 - 前記支持円筒および前記炉心は、予め組み立てられて原子炉設置場所に輸送される、請求項1に記載の原子炉炉心支持システム。
- 前記支持円筒内において燃料要素ハンドリングシステムをさらに備える、請求項1に記載の原子炉炉心支持システム。
- 前記支持円筒内において制御要素支持システムをさらに備える、請求項1に記載の原子炉炉心支持システム。
- 前記支持円筒および制御要素駆動システムは、共通の荷重経路を共有する、請求項1に記載の原子炉炉心支持システム。
- 前記支持円筒および前記制御要素駆動システムは共に、前記原子炉容器ヘッドのある部分から吊り下げられている、請求項5に記載の原子炉炉心支持システム。
- 前記支持円筒内に配置された炉心の支持体は、前記原子炉容器に荷重を伝達しない、請求項1に記載の原子炉炉心支持システム。
- 炉心が前記支持円筒内に配置され、前記炉心の重量が前記原子炉容器ヘッドに支持される、請求項1に記載の原子炉炉心支持システム。
Priority Applications (1)
| Application Number | Priority Date | Filing Date | Title |
|---|---|---|---|
| JP2025060912A JP2025096334A (ja) | 2020-08-17 | 2025-04-02 | 原子炉用カートリッジ炉心バレル |
Applications Claiming Priority (5)
| Application Number | Priority Date | Filing Date | Title |
|---|---|---|---|
| US202063066785P | 2020-08-17 | 2020-08-17 | |
| US63/066,785 | 2020-08-17 | ||
| US17/164,820 | 2021-02-01 | ||
| US17/164,820 US11728049B2 (en) | 2020-08-17 | 2021-02-01 | Reactor core and control elements supported by a reactor vessel head |
| PCT/US2021/022017 WO2022039790A1 (en) | 2020-08-17 | 2021-03-11 | Cartridge core barrel for nuclear reactor |
Related Child Applications (1)
| Application Number | Title | Priority Date | Filing Date |
|---|---|---|---|
| JP2025060912A Division JP2025096334A (ja) | 2020-08-17 | 2025-04-02 | 原子炉用カートリッジ炉心バレル |
Publications (2)
| Publication Number | Publication Date |
|---|---|
| JP2023538028A JP2023538028A (ja) | 2023-09-06 |
| JP7661482B2 true JP7661482B2 (ja) | 2025-04-14 |
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Family Applications (5)
| Application Number | Title | Priority Date | Filing Date |
|---|---|---|---|
| JP2023511815A Active JP7602017B2 (ja) | 2020-08-17 | 2021-03-04 | 原子炉の受動的熱除去システム |
| JP2023511582A Active JP7661482B2 (ja) | 2020-08-17 | 2021-03-11 | 原子炉用カートリッジ炉心バレル |
| JP2023511825A Active JP7719858B2 (ja) | 2020-08-17 | 2021-04-01 | 曲線電磁ポンプ |
| JP2023511813A Active JP7594094B2 (ja) | 2020-08-17 | 2021-04-06 | 電磁ポンプ用慣性エネルギーコーストダウン |
| JP2025060912A Pending JP2025096334A (ja) | 2020-08-17 | 2025-04-02 | 原子炉用カートリッジ炉心バレル |
Family Applications Before (1)
| Application Number | Title | Priority Date | Filing Date |
|---|---|---|---|
| JP2023511815A Active JP7602017B2 (ja) | 2020-08-17 | 2021-03-04 | 原子炉の受動的熱除去システム |
Family Applications After (3)
| Application Number | Title | Priority Date | Filing Date |
|---|---|---|---|
| JP2023511825A Active JP7719858B2 (ja) | 2020-08-17 | 2021-04-01 | 曲線電磁ポンプ |
| JP2023511813A Active JP7594094B2 (ja) | 2020-08-17 | 2021-04-06 | 電磁ポンプ用慣性エネルギーコーストダウン |
| JP2025060912A Pending JP2025096334A (ja) | 2020-08-17 | 2025-04-02 | 原子炉用カートリッジ炉心バレル |
Country Status (7)
| Country | Link |
|---|---|
| US (9) | US11798697B2 (ja) |
| EP (4) | EP4197004A1 (ja) |
| JP (5) | JP7602017B2 (ja) |
| KR (3) | KR20230049127A (ja) |
| CN (4) | CN116114034A (ja) |
| CA (4) | CA3187043A1 (ja) |
| WO (4) | WO2022039787A1 (ja) |
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| Publication number | Priority date | Publication date | Assignee | Title |
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| WO2023049690A1 (en) | 2021-09-21 | 2023-03-30 | Abilene Christian University | Stabilizing face ring joint flange and assembly thereof |
| FR3131060B1 (fr) * | 2021-12-16 | 2023-12-08 | Commissariat Energie Atomique | Réacteur nucléaire refroidi au métal liquide intégrant un système passif d’évacuation de la puissance résiduelle (EPUR) à source froide avec réservoir thermique à matériau à changement de phase (MCP) et couche isolante thermique amovible autour du réservoir à MCP. |
| CN115263049B (zh) * | 2022-07-29 | 2024-01-09 | 中国核工业华兴建设有限公司 | 一种核电站大直径堆芯碳钢竖井一体式模块结构及其施工方法 |
| KR102736309B1 (ko) * | 2022-10-14 | 2024-11-29 | 한국수력원자력 주식회사 | 일체형 원자로 취급시스템 |
| US12562289B2 (en) | 2023-01-20 | 2026-02-24 | Abilene Christian University | Fission product trap for salt pipe and pump shaft seals and methods of use thereof |
| US12249434B2 (en) | 2023-03-31 | 2025-03-11 | Abilene Christian University | Thermal expansion support system and methods of use thereof |
| WO2025015124A2 (en) | 2023-07-11 | 2025-01-16 | Abilene Christian University | Nuclear reactor fluid level control system |
| US12444514B2 (en) | 2023-08-07 | 2025-10-14 | Abilene Christian University | Calibration of power monitors in molten salt reactors |
| US12327648B2 (en) | 2023-08-14 | 2025-06-10 | Natura Resources LLC | Molten salt reactor containment |
| US12012827B1 (en) | 2023-09-11 | 2024-06-18 | Natura Resources LLC | Nuclear reactor integrated oil and gas production systems and methods of operation |
| US12500006B2 (en) | 2023-12-05 | 2025-12-16 | Natura Resources LLC | Deployment method and systems for molten salt reactors |
| US12596817B2 (en) | 2023-12-08 | 2026-04-07 | The Texas A&M University System | Secure remote controls package for semi-autonomous systems |
| US20250279698A1 (en) * | 2024-02-29 | 2025-09-04 | Ge Infrastructure Technology Llc | Electric machine with integrated electromagnetic pumping scheme for direct cooled windings |
Citations (2)
| Publication number | Priority date | Publication date | Assignee | Title |
|---|---|---|---|---|
| JP2000346970A (ja) | 1999-06-02 | 2000-12-15 | Japan Nuclear Cycle Development Inst States Of Projects | 炉心槽回転式原子炉構造 |
| JP2007502425A (ja) | 2003-08-15 | 2007-02-08 | ぺブル ベッド モジュラー リアクター (プロプリエタリー)リミテッド | 支持装置 |
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