JP2022063014A - 原子炉ユニット及び原子炉ユニットの冷却方法 - Google Patents
原子炉ユニット及び原子炉ユニットの冷却方法 Download PDFInfo
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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
- G21C15/10—Arrangements or disposition of passages in which heat is transferred to the coolant; Coolant flow control devices from reflector or thermal shield
-
- 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
-
- G—PHYSICS
- G21—NUCLEAR PHYSICS; NUCLEAR ENGINEERING
- G21C—NUCLEAR REACTORS
- G21C13/00—Pressure vessels; Containment vessels; Containment in general
- G21C13/02—Details
- G21C13/022—Ventilating arrangements
-
- 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
- G21C15/20—Partitions or thermal insulation between fuel channel and moderator
-
- 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
- G21C7/00—Control of nuclear reaction
- G21C7/28—Control of nuclear reaction by displacement of the reflector or parts thereof
-
- 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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- Physics & Mathematics (AREA)
- Engineering & Computer Science (AREA)
- Plasma & Fusion (AREA)
- General Engineering & Computer Science (AREA)
- High Energy & Nuclear Physics (AREA)
- Monitoring And Testing Of Nuclear Reactors (AREA)
- Structure Of Emergency Protection For Nuclear Reactors (AREA)
Abstract
Description
図1は、本実施形態に係る原子炉ユニットの一例である原子力発電システムの模式図である。図1に示すように、原子力発電システム50は、原子炉容器51と、熱交換器52と、熱伝導部53と、冷媒循環手段54と、タービン55と、発電機56と、冷却器57と、圧縮機58と、を有する。
また、第2空間112は、第1空間110よりも真空度が低い空間であり、例えば圧力が0.1MPa以上0.4MPa以下となる。また、第2空間112は、炉心1が配置されている空間であるため、窒素等の不活性ガスを充填することが好ましい。
2 遮蔽部
3 熱伝導部
4 制御部
6 断熱部
11 原子炉
50 原子力発電システム(原子炉ユニット)
51 原子炉容器
52 熱交換器
53 熱伝導部
54 冷媒循環手段
55 タービン
56 発電機
57 冷却器
58 圧縮機
102 外側隔壁
104 内側隔壁
106 本体部
108、108a 連通部(埋設部)
109 穴
110 第1空間
112 第2空間
130、132、134、180 流れ
150、170 連通部
160 板部
162、172 板本体
164、174 回動軸
166、168、176、178 ろう接部
Claims (9)
- 放射性燃料を有し、前記放射性燃料を核反応させる炉心と、
前記炉心を格納し、前記炉心を密閉する原子炉容器と、を備え、
前記原子炉容器は、前記炉心の周囲全域を覆う内側隔壁と、前記内側隔壁の周囲全域を覆う外側隔壁と、を含み、
前記外側隔壁と前記内側隔壁とで形成される第1空間が真空状態であり、
前記内側隔壁は、本体部と、前記本体部の一部に配置され、前記炉心が閾値温度以上となった場合に、前記内側隔壁の内側の空間である第2空間と前記第1空間と連通させる連通部とを備える原子炉ユニット。 - 前記連通部は、前記本体部よりも融点の低い材料で形成され、前記本体部に形成された穴を埋める埋設部を備え、前記閾値温度以上となり前記第2空間の温度が上昇した場合、前記本体部の穴を開口させる請求項1に記載の原子炉ユニット。
- 前記埋設部は、前記閾値温度以上となり前記第2空間の温度が上昇した場合に溶融する金属である請求項2に記載の原子炉ユニット。
- 前記埋設部は、前記閾値温度以上になると前記第1空間と前記第2空間の差圧により破壊され、前記本体部の穴を開口させる請求項2に記載の原子炉ユニット。
- 前記連通部は、前記本体部の穴に配置され、前記本体部に対して回動可能な板部と、前記本体部よりも融点の低い材料で形成され、前記板部を前記本体部に対して結合する結合部と、を含み
前記炉心が前記閾値温度以上となり前記第2空間の温度が上昇した場合、前記結合部が、前記本体部及び前記板部の少なくとも一方から外れる請求項1に記載の原子炉ユニット。 - 前記結合部は、閾値温度以上となり前記第2空間の温度が上昇した場合に溶融する金属である請求項5に記載の原子炉ユニット。
- 前記板部は、回動する軸が、前記板部の重心を通らない請求項5または請求項6に記載の原子炉ユニット。
- 前記炉心で発生した熱を前記原子炉容器の外に固体熱伝導で伝える熱伝導部を有する請求項1から請求項7のいずれか一項に記載の原子炉ユニット。
- 放射性燃料を有し、前記放射性燃料を核反応させる炉心と、前記炉心を格納し、前記炉心を密閉する原子炉容器と、を備える原子炉ユニットの冷却方法であって、
前記原子炉容器は、前記炉心の周囲全域を覆う内側隔壁と、前記内側隔壁の周囲全域を覆う外側隔壁と、を含み、前記外側隔壁と前記内側隔壁とで形成される第1空間が真空状態であり、
前記内側隔壁は、本体部と、前記本体部の一部に配置された連通部を備え、
前記炉心が閾値温度以上となった場合に、前記連通部が、前記内側隔壁の内側の空間である第2空間と前記第1空間と連通させ、前記第1空間の真空状態を破壊する原子炉ユニットの冷却方法。
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JP2020171289A JP7499139B2 (ja) | 2020-10-09 | 2020-10-09 | 原子炉ユニット及び原子炉ユニットの冷却方法 |
PCT/JP2021/034623 WO2022075058A1 (ja) | 2020-10-09 | 2021-09-21 | 原子炉ユニット及び原子炉ユニットの冷却方法 |
US18/028,591 US20230360812A1 (en) | 2020-10-09 | 2021-09-21 | Nuclear reactor unit and method for cooling nuclear reactor unit |
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JPH08511103A (ja) * | 1993-06-08 | 1996-11-19 | シーメンス アクチエンゲゼルシヤフト | 炉心溶融物の冷却を開始するための閉塞装置 |
US8687759B2 (en) | 2007-11-15 | 2014-04-01 | The State Of Oregon Acting By And Through The State Board Of Higher Education On Behalf Of Oregon State University | Internal dry containment vessel for a nuclear reactor |
US8571167B2 (en) | 2009-06-01 | 2013-10-29 | Advanced Reactor Concepts LLC | Particulate metal fuels used in power generation, recycling systems, and small modular reactors |
US10672522B2 (en) | 2015-02-09 | 2020-06-02 | Westinghouse Electric Company Llc | Magneto-rheological fluid based filter/reflector |
JP2016223865A (ja) | 2015-05-29 | 2016-12-28 | 日立Geニュークリア・エナジー株式会社 | 温度応動弁、原子力発電プラント及び温度応動弁用低融点金属 |
GB201820328D0 (en) | 2018-12-13 | 2019-01-30 | Rolls Royce Plc | Depressurisation valve |
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