JP2023535186A - 被動補助給水系統の不用熱交換水活用システム及び被動補助給水系統の不用熱交換水を活用した原子炉冷却制御方法 - Google Patents
被動補助給水系統の不用熱交換水活用システム及び被動補助給水系統の不用熱交換水を活用した原子炉冷却制御方法 Download PDFInfo
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- XLYOFNOQVPJJNP-UHFFFAOYSA-N water Substances O XLYOFNOQVPJJNP-UHFFFAOYSA-N 0.000 title claims abstract description 242
- 238000001816 cooling Methods 0.000 title claims abstract description 24
- 238000000034 method Methods 0.000 title claims abstract description 22
- 238000011084 recovery Methods 0.000 claims abstract description 24
- 239000002918 waste heat Substances 0.000 claims abstract description 17
- 239000000498 cooling water Substances 0.000 claims abstract description 15
- 238000009833 condensation Methods 0.000 claims description 18
- 230000005494 condensation Effects 0.000 claims description 18
- 238000005259 measurement Methods 0.000 claims description 6
- 230000004044 response Effects 0.000 abstract description 3
- 230000008569 process Effects 0.000 description 9
- 230000009471 action Effects 0.000 description 6
- 238000005086 pumping Methods 0.000 description 6
- 230000007423 decrease Effects 0.000 description 4
- 238000010586 diagram Methods 0.000 description 3
- 230000004048 modification Effects 0.000 description 3
- 238000012986 modification Methods 0.000 description 3
- 230000000694 effects Effects 0.000 description 2
- 238000001704 evaporation Methods 0.000 description 2
- 238000012546 transfer Methods 0.000 description 2
- 230000004075 alteration Effects 0.000 description 1
- 230000008901 benefit Effects 0.000 description 1
- 239000002826 coolant Substances 0.000 description 1
- 230000010485 coping Effects 0.000 description 1
- 230000003247 decreasing effect Effects 0.000 description 1
- 238000013461 design Methods 0.000 description 1
- 238000001514 detection method Methods 0.000 description 1
- 230000005611 electricity Effects 0.000 description 1
- 230000008020 evaporation Effects 0.000 description 1
- 230000004992 fission Effects 0.000 description 1
- 239000000446 fuel Substances 0.000 description 1
- 239000003758 nuclear fuel Substances 0.000 description 1
- 238000013021 overheating Methods 0.000 description 1
- 230000002265 prevention Effects 0.000 description 1
- 239000012857 radioactive material Substances 0.000 description 1
- 230000007480 spreading Effects 0.000 description 1
- 239000008400 supply water Substances 0.000 description 1
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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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- F—MECHANICAL ENGINEERING; LIGHTING; HEATING; WEAPONS; BLASTING
- F22—STEAM GENERATION
- F22B—METHODS OF STEAM GENERATION; STEAM BOILERS
- F22B37/00—Component parts or details of steam boilers
- F22B37/002—Component parts or details of steam boilers specially adapted for nuclear steam generators, e.g. maintenance, repairing or inspecting equipment not otherwise provided for
-
- F—MECHANICAL ENGINEERING; LIGHTING; HEATING; WEAPONS; BLASTING
- F22—STEAM GENERATION
- F22B—METHODS OF STEAM GENERATION; STEAM BOILERS
- F22B37/00—Component parts or details of steam boilers
- F22B37/02—Component parts or details of steam boilers applicable to more than one kind or type of steam boiler
- F22B37/26—Steam-separating arrangements
- F22B37/268—Steam-separating arrangements specially adapted for steam generators of nuclear power plants
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- G—PHYSICS
- G01—MEASURING; TESTING
- G01F—MEASURING VOLUME, VOLUME FLOW, MASS FLOW OR LIQUID LEVEL; METERING BY VOLUME
- G01F23/00—Indicating or measuring liquid level or level of fluent solid material, e.g. indicating in terms of volume or indicating by means of an alarm
- G01F23/0007—Indicating or measuring liquid level or level of fluent solid material, e.g. indicating in terms of volume or indicating by means of an alarm for discrete indicating and measuring
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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
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- G—PHYSICS
- G21—NUCLEAR PHYSICS; NUCLEAR ENGINEERING
- G21D—NUCLEAR POWER PLANT
- G21D1/00—Details of nuclear power plant
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- G—PHYSICS
- G21—NUCLEAR PHYSICS; NUCLEAR ENGINEERING
- G21D—NUCLEAR POWER PLANT
- G21D3/00—Control of nuclear power plant
- G21D3/04—Safety arrangements
- G21D3/06—Safety arrangements responsive to faults within the plant
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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)
- High Energy & Nuclear Physics (AREA)
- General Engineering & Computer Science (AREA)
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Abstract
Description
これを達成するために、原子力発電所は、事故発生の際に発電所を安全に停止させることができるように工学的安全設備系統を備えている。工学的安全設備系統は、格納容器系統(Containment System)、非常用炉心冷却系統(Emergency Core Cooling System)、及び被動補助給水系統(Passive Auxiliary Feedwater System)を含む。
Claims (6)
- 原子炉の熱によって蒸気を発生させる蒸気発生器と、熱交換水が貯水された被動凝縮タンクと、前記被動凝縮タンクの内部に設置され、被動凝縮タンクの底から離間して設けられた凝縮器と、蒸気発生器と被動凝縮タンクの凝縮器の入口との間に設置され、原子炉運転中断の際にタービン側への蒸気供給を遮断し、前記凝縮器へ蒸気を分岐させる管路を提供する蒸気供給管と、前記凝縮器の出口と前記蒸気発生器との間に設置され、凝縮器を介して凝縮した凝縮水を蒸気発生器に回収させる管路を提供する凝縮水回収管と、を含む、原子力発電施設の被動補助給水系統において、
前記被動凝縮タンクと前記凝縮水回収管との間には、前記凝縮器と前記被動凝縮タンクの底との間に残った残水が前記凝縮水回収管へ排出されるように残水排出流路が設置されたことを特徴とする、被動補助給水系統の不用熱交換水活用システム。 - 前記残水排出流路は、前記被動凝縮タンクの最低点に連結されたことを特徴とする、請求項1に記載の被動補助給水系統の不用熱交換水活用システム。
- 前記残水排出流路から排出される残水は、前記凝縮水回収管へ自然落下できるように構成されたことを特徴とする、請求項1又は2に記載の被動補助給水系統の不用熱交換水活用システム。
- 前記被動凝縮タンクには、熱交換水の水位を測定する水位測定センサが設置され、前記残水排出流路には、自動弁が設置され、
前記自動弁は、水位測定センサの水位検知によって残水排出流路を自動的に開放させることができるように設置されたことを特徴とする、請求項1又は2に記載の被動補助給水系統の不用熱交換水活用システム。 - 原子炉事故の発生の際に、蒸気発生器の蒸気が凝縮器へ供給されるステップと、
凝縮器から凝縮した凝縮水が冷却水として原子炉側へ供給されるステップと、
被動凝縮タンクの水位が測定されるステップと、
被動凝縮タンの熱交換水の水位に応じて、残水排出流路が開放されて被動凝縮タンクの熱交換水が冷却水として原子炉に供給されるステップと、を含む、被動補助給水系統の不用熱交換水を活用した原子炉冷却制御方法。 - 前記被動凝縮タンクの熱交換水は、凝縮水回収管へ自然落下することを特徴とする、請求項5に記載の被動補助給水系統の不用熱交換水を活用した原子炉冷却制御方法。
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KR1020200091357A KR102455236B1 (ko) | 2020-07-23 | 2020-07-23 | 피동보조급수계통의 불용 열교환수 활용 시스템 |
KR10-2020-0091357 | 2020-07-23 | ||
PCT/KR2021/008919 WO2022019555A1 (ko) | 2020-07-23 | 2021-07-12 | 피동보조급수계통의 불용 열교환수 활용 시스템 및 피동보조급수계통의 불용 열교환수를 활용한 원자로 냉각 제어방법 |
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US (1) | US20230290529A1 (ja) |
EP (1) | EP4187552A1 (ja) |
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JP5235614B2 (ja) | 2008-11-05 | 2013-07-10 | 日立Geニュークリア・エナジー株式会社 | 原子力プラント及び制御方法 |
KR101022164B1 (ko) | 2009-06-15 | 2011-03-17 | 한국수력원자력 주식회사 | 경수로의 피동형 이차측 응축계통 |
KR101221812B1 (ko) * | 2011-08-30 | 2013-01-14 | 한국수력원자력 주식회사 | 수위 조절이 가능한 피동형 보충수 탱크 |
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WO2022019555A1 (ko) | 2022-01-27 |
KR102455236B1 (ko) | 2022-10-18 |
KR20220012510A (ko) | 2022-02-04 |
JP7480418B2 (ja) | 2024-05-09 |
US20230290529A1 (en) | 2023-09-14 |
EP4187552A1 (en) | 2023-05-31 |
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