JP7488955B2 - 災害事故原子炉冷却システム及びこれを用いた原子炉冷却方法 - Google Patents
災害事故原子炉冷却システム及びこれを用いた原子炉冷却方法 Download PDFInfo
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- JP7488955B2 JP7488955B2 JP2023504444A JP2023504444A JP7488955B2 JP 7488955 B2 JP7488955 B2 JP 7488955B2 JP 2023504444 A JP2023504444 A JP 2023504444A JP 2023504444 A JP2023504444 A JP 2023504444A JP 7488955 B2 JP7488955 B2 JP 7488955B2
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- 238000001816 cooling Methods 0.000 title claims description 39
- XLYOFNOQVPJJNP-UHFFFAOYSA-N water Substances O XLYOFNOQVPJJNP-UHFFFAOYSA-N 0.000 claims description 100
- 239000013535 sea water Substances 0.000 claims description 95
- 238000007599 discharging Methods 0.000 claims description 8
- 238000000034 method Methods 0.000 claims description 7
- 239000000498 cooling water Substances 0.000 description 11
- 238000005086 pumping Methods 0.000 description 5
- 239000012857 radioactive material Substances 0.000 description 5
- 230000008569 process Effects 0.000 description 3
- 230000000694 effects Effects 0.000 description 2
- 238000012986 modification Methods 0.000 description 2
- 230000004048 modification Effects 0.000 description 2
- 239000003758 nuclear fuel Substances 0.000 description 2
- 238000006243 chemical reaction Methods 0.000 description 1
- 238000002485 combustion reaction Methods 0.000 description 1
- 238000010586 diagram Methods 0.000 description 1
- 230000005611 electricity Effects 0.000 description 1
- 230000008451 emotion Effects 0.000 description 1
- 238000003912 environmental pollution Methods 0.000 description 1
- 238000004880 explosion Methods 0.000 description 1
- 230000004992 fission Effects 0.000 description 1
- 230000036541 health Effects 0.000 description 1
- 239000012768 molten material Substances 0.000 description 1
- 238000013021 overheating Methods 0.000 description 1
- 238000010248 power generation Methods 0.000 description 1
- 230000002285 radioactive effect Effects 0.000 description 1
- 239000002689 soil Substances 0.000 description 1
- 230000002459 sustained effect Effects 0.000 description 1
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Classifications
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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
-
- 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
-
- 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
-
- 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
-
- 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
-
- 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
- Y10—TECHNICAL SUBJECTS COVERED BY FORMER USPC
- Y10S—TECHNICAL SUBJECTS COVERED BY FORMER USPC CROSS-REFERENCE ART COLLECTIONS [XRACs] AND DIGESTS
- Y10S376/00—Induced nuclear reactions: processes, systems, and elements
- Y10S376/912—Nuclear reactor systems situated in the ocean
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- Physics & Mathematics (AREA)
- Engineering & Computer Science (AREA)
- Plasma & Fusion (AREA)
- General Engineering & Computer Science (AREA)
- High Energy & Nuclear Physics (AREA)
- Structure Of Emergency Protection For Nuclear Reactors (AREA)
Description
Claims (5)
- 原子力発電施設と、
海水を貯水させることができるように貯水空間を提供する海水貯蔵タンクと、
前記海水貯蔵タンクの一側と他側にそれぞれ設置され、海水貯蔵タンクに海水を流入させることが可能な管路を提供する海水流入流路、及び海水貯蔵タンクから海水を海に排出させることができるように管路を提供する海水排出流路と、
前記海水貯蔵タンクの貯水空間に設置された熱交換器と、
重大事故発生の際に前記原子力発電施設から発生した汚染水が熱交換器へ移送されるように管路を提供する汚染水供給流路と、
前記熱交換器と前記原子力発電施設との間に設置され、熱交換器を介して海水貯蔵タンクの海水と熱交換された汚染水が原子力発電施設へ排出されるように管路を提供する汚染水排出流路と、を含み、
前記熱交換器は、前記海水貯蔵タンクの高さ方向に積層され、前記熱交換器を通る汚染水と海水との相互接触面積を増やすことができるように構成され、
前記汚染水供給流路と前記汚染水排出流路との間の熱交換器管路は、前記熱交換器のプレート状の筐体に覆われて海水にさらされないように構成され、
前記熱交換器の前記筐体は、側面から見たときに、ジグザグ方向に一体に形成され、前記海水貯蔵タンクの底に対して傾斜して形成されたことを特徴とする、災害事故原子炉冷却システム。 - 前記原子力発電施設から発生した汚染水は、原子力発電施設と熱交換器を循環し、海水は、海と海水貯蔵タンクを循環することを特徴とする、請求項1に記載の災害事故原子炉冷却システム。
- 熱交換器が海水貯蔵タンクの貯水空間に設置され、
重大事故の際に原子力発電施設から発生した汚染水が熱交換器と原子力発電施設を循環するステップと、
海水が海と海水貯蔵タンクを循環するステップと、
熱交換された汚染水が原子力発電施設の内部へ噴射されるステップと、を含む、災害事故原子炉冷却システムを用いた原子炉冷却方法。 - 前記汚染水は、積層された熱交換器の最上部から熱交換器の最下部に自然落下するが、熱交換器の傾斜角に沿って落下し、最下部に落下した汚染水は、ポンプを介して原子力発電施設に向かって排出されることを特徴とする、請求項3に記載の災害事故原子炉冷却システムを用いた原子炉冷却方法。
- 前記熱交換器は、前記海水貯蔵タンクの高さ方向に積層され、前記熱交換器を通る汚染水と海水との相互接触面積を増やすことができるように構成され、
重大事故発生の際に前記原子力発電施設から発生した汚染水が前記熱交換器へ移送されるように管路を提供する汚染水供給流路と、前記熱交換器と前記原子力発電施設との間に設置され、前記熱交換器を介して前記海水貯蔵タンクの海水と熱交換された汚染水が前記原子力発電施設へ排出されるように管路を提供する汚染水排出流路との間に、熱交換器管路を含み、
前記熱交換器管路は、前記熱交換器のプレート状の筐体に覆われて海水にさらされないように構成され、
前記熱交換器の前記筐体は、側面から見たときに、ジグザグ方向に一体に形成され、前記海水貯蔵タンクの底に対して傾斜して形成されたことを特徴とする、請求項4に記載の災害事故原子炉冷却システムを用いた原子炉冷却方法。
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KR10-2020-0090162 | 2020-07-21 | ||
KR1020200090162A KR102455235B1 (ko) | 2020-07-21 | 2020-07-21 | 재해사고 원자로 냉각 시스템 및 이를 이용한 원자로 냉각 방법 |
PCT/KR2021/008917 WO2022019554A1 (ko) | 2020-07-21 | 2021-07-12 | 재해사고 원자로 냉각 시스템 및 이를 이용한 원자로 냉각 방법 |
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JP2023535185A JP2023535185A (ja) | 2023-08-16 |
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EP (1) | EP4187554A1 (ja) |
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WO (1) | WO2022019554A1 (ja) |
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Citations (2)
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JP2012230085A (ja) | 2011-04-27 | 2012-11-22 | Toshiba Corp | 原子力プラント |
JP2013096927A (ja) | 2011-11-04 | 2013-05-20 | Hitachi-Ge Nuclear Energy Ltd | 原子力発電プラントの非常用復水器 |
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JPH08146184A (ja) * | 1994-09-19 | 1996-06-07 | Toshiba Corp | 原子炉格納容器 |
JPH1020081A (ja) * | 1996-07-09 | 1998-01-23 | Toshiba Corp | 原子力発電所の海水冷却系設備 |
KR101241142B1 (ko) * | 2011-09-09 | 2013-03-19 | 세화엠피(주) | 원자로 비상냉각용 해수담수화시스템 |
KR101405666B1 (ko) * | 2012-11-14 | 2014-06-10 | 한국수력원자력 주식회사 | 원자력 발전소의 피동이차응축시스템 |
KR101742290B1 (ko) | 2016-01-28 | 2017-05-30 | 삼성중공업 주식회사 | 원자로 비상냉각 시스템 |
KR102051573B1 (ko) * | 2018-04-05 | 2019-12-05 | 한국원자력연구원 | 통합 기기냉각 계통 및 통합 기기냉각 계통의 냉각 방법 |
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- 2021-07-12 WO PCT/KR2021/008917 patent/WO2022019554A1/ko unknown
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Publication number | Priority date | Publication date | Assignee | Title |
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JP2012230085A (ja) | 2011-04-27 | 2012-11-22 | Toshiba Corp | 原子力プラント |
JP2013096927A (ja) | 2011-11-04 | 2013-05-20 | Hitachi-Ge Nuclear Energy Ltd | 原子力発電プラントの非常用復水器 |
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EP4187554A1 (en) | 2023-05-31 |
US20230307150A1 (en) | 2023-09-28 |
KR20220011364A (ko) | 2022-01-28 |
KR102455235B1 (ko) | 2022-10-18 |
WO2022019554A1 (ko) | 2022-01-27 |
JP2023535185A (ja) | 2023-08-16 |
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