JP7443394B2 - 沸騰水型原子炉における炉心流量、炉心出力、および圧力を制限するための非常用復水器および/または給水の使用 - Google Patents
沸騰水型原子炉における炉心流量、炉心出力、および圧力を制限するための非常用復水器および/または給水の使用 Download PDFInfo
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- XLYOFNOQVPJJNP-UHFFFAOYSA-N water Substances O XLYOFNOQVPJJNP-UHFFFAOYSA-N 0.000 title claims description 67
- 238000009835 boiling Methods 0.000 title claims description 28
- 238000000034 method Methods 0.000 claims description 9
- 230000002093 peripheral effect Effects 0.000 claims 2
- 230000004044 response Effects 0.000 description 8
- 230000000694 effects Effects 0.000 description 6
- 239000012530 fluid Substances 0.000 description 5
- 230000007246 mechanism Effects 0.000 description 4
- 238000004088 simulation Methods 0.000 description 4
- 239000000446 fuel Substances 0.000 description 3
- 239000007788 liquid Substances 0.000 description 3
- 230000000116 mitigating effect Effects 0.000 description 3
- 238000000926 separation method Methods 0.000 description 3
- 238000010248 power generation Methods 0.000 description 2
- 230000008569 process Effects 0.000 description 2
- 230000008901 benefit Effects 0.000 description 1
- KGBXLFKZBHKPEV-UHFFFAOYSA-N boric acid Chemical compound OB(O)O KGBXLFKZBHKPEV-UHFFFAOYSA-N 0.000 description 1
- 239000004327 boric acid Substances 0.000 description 1
- 238000004364 calculation method Methods 0.000 description 1
- 238000004891 communication Methods 0.000 description 1
- 230000005494 condensation Effects 0.000 description 1
- 238000009833 condensation Methods 0.000 description 1
- 238000001816 cooling Methods 0.000 description 1
- 239000000498 cooling water Substances 0.000 description 1
- 230000003247 decreasing effect Effects 0.000 description 1
- 238000013461 design Methods 0.000 description 1
- 238000010586 diagram Methods 0.000 description 1
- 238000011156 evaluation Methods 0.000 description 1
- 230000004992 fission Effects 0.000 description 1
- 238000010438 heat treatment Methods 0.000 description 1
- 238000002347 injection Methods 0.000 description 1
- 239000007924 injection Substances 0.000 description 1
- 238000012986 modification Methods 0.000 description 1
- 230000004048 modification Effects 0.000 description 1
- 238000005086 pumping Methods 0.000 description 1
- 230000009257 reactivity Effects 0.000 description 1
- 230000009467 reduction Effects 0.000 description 1
- 230000000630 rising effect Effects 0.000 description 1
- 229920006395 saturated elastomer Polymers 0.000 description 1
- 239000008400 supply water Substances 0.000 description 1
- 239000002351 wastewater 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
- 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
- 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
- G21C1/084—Boiling water reactors
-
- 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
- G21C7/00—Control of nuclear reaction
- G21C7/32—Control of nuclear reaction by varying flow of coolant through the core by adjusting the coolant or moderator temperature
-
- G—PHYSICS
- G21—NUCLEAR PHYSICS; NUCLEAR ENGINEERING
- G21D—NUCLEAR POWER PLANT
- G21D3/00—Control of nuclear power plant
- G21D3/08—Regulation of any parameters in the plant
- G21D3/12—Regulation of any parameters in the plant by adjustment of the reactor in response only to changes in engine demand
- G21D3/14—Varying flow of coolant
-
- 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
-
- 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
- G21C15/25—Promoting flow of the coolant for liquids using jet pumps
-
- G—PHYSICS
- G21—NUCLEAR PHYSICS; NUCLEAR ENGINEERING
- G21D—NUCLEAR POWER PLANT
- G21D5/00—Arrangements of reactor and engine in which reactor-produced heat is converted into mechanical energy
- G21D5/04—Reactor and engine not structurally combined
- G21D5/06—Reactor and engine not structurally combined with engine working medium circulating through reactor core
-
- 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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- Plasma & Fusion (AREA)
- General Engineering & Computer Science (AREA)
- High Energy & Nuclear Physics (AREA)
- Chemical & Material Sciences (AREA)
- Chemical Kinetics & Catalysis (AREA)
- Structure Of Emergency Protection For Nuclear Reactors (AREA)
Description
Claims (11)
- 原子炉圧力容器と、
前記原子炉圧力容器内に配置された炉心と、
前記炉心を包囲する炉心シュラウドと、
前記原子炉圧力容器の内周面と前記炉心シュラウドとの間に配置された下降管領域と、
前記原子炉圧力容器の上端部に接続された蒸気ラインと、
前記原子炉圧力容器から蒸気を受承し、また、前記炉心上部の前記炉心シュラウド内にて復水を前記炉心シュラウドの上部プレナムまたは煙突領域の一方または両者に直接戻すとともに前記炉心シュラウドに直接接続される復水戻りラインを含む非常用復水器システムであって、前記非常用復水器システムは、いずれのタービンにも接続されず、前記復水戻りラインは、原子炉停止中に前記復水戻りラインを通る流れを開放する弁を含む、非常用復水器システムと、
を備える、沸騰水型原子炉システム。 - 前記復水戻りラインは、前記下降管領域内の復水を戻す分岐部をさらに含む、請求項1に記載の沸騰水型原子炉システム。
- 前記原子炉圧力容器からの蒸気を受承するタービンと、
前記タービンからの前記蒸気を受承する主復水器システムであって、同主復水器システムが、前記主復水器システムから復水を戻すための給水戻りラインによって、前記原子炉圧力容器に接続されている、主復水器システムと、
をさらに備える、請求項1に記載の沸騰水型原子炉システム。 - 前記給水戻りラインは、前記炉心上部の前記炉心シュラウド内にて復水を、前記炉心シュラウドの上部プレナムまたは煙突領域の一方または両者に戻す、請求項3に記載の沸騰水型原子炉システム。
- 前記給水戻りラインは、前記下降管内部の復水を戻す第1分岐部を含む、請求項4に記載の沸騰水型原子炉システム。
- 前記給水戻りラインは、前記下降管内部の復水を戻す、請求項3に記載の沸騰水型原子炉システム。
- 原子炉圧力容器と、
前記原子炉圧力容器内に配置された炉心と、
前記炉心を包囲する炉心シュラウドと、
前記原子炉圧力容器の内周面と前記炉心シュラウドとの間に配置された下降管領域と、
前記原子炉圧力容器の上端部に接続された蒸気ラインと、
前記原子炉圧力容器からの蒸気を受承するタービンと、
前記タービンからの蒸気を受承する主復水器システムであって、同主復水器システムから復水を戻すための給水戻りラインによって前記原子炉圧力容器に接続され、前記給水戻りラインは、前記炉心上部の前記炉心シュラウド内にて復水を、前記炉心シュラウドの上部プレナムまたは煙突領域の一方または両者に戻す、主復水器システムと、
前記原子炉圧力容器から蒸気を受承し、また、前記炉心上部の前記炉心シュラウド内にて復水を前記炉心シュラウドの上部プレナムまたは煙突領域の一方または両者に直接戻すとともに前記炉心シュラウドに直接接続される復水戻りラインを含む非常用復水器システムであって、前記非常用復水器システムは、いずれのタービンにも接続されず、前記復水戻りラインは、原子炉停止中に前記復水戻りラインを通る流れを開放する弁を含む、非常用復水器システムと、
を備える、沸騰水型原子炉システム。 - 前記給水戻りラインは、前記下降管内部の復水を戻す第1分岐部を含む、請求項7に記載の沸騰水型原子炉システム。
- 前記復水戻りラインは、前記下降管領域内の復水を戻す分岐部をさらに含む、請求項7に記載の沸騰水型原子炉システム。
- 原子炉圧力容器と、前記原子炉圧力容器内に配置された炉心と、前記炉心を包囲する炉心シュラウドと、前記原子炉圧力容器の内面と前記炉心シュラウドとの間に配置された下降管領域と、前記原子炉圧力容器の上端部およびタービンに直接接続された第1の蒸気ラインと、前記タービンから蒸気を受承する第1の復水器システムと、前記タービンに接続されていない第2の蒸気ラインであって、前記原子炉圧力容器の前記上端部、並びに前記第1の復水器システムとは別体の第2の非常用復水器システムに直接接続されている第2の蒸気ラインとを有し、前記原子炉圧力容器から蒸気が前記第2の蒸気ラインを通って前記第2の非常用復水器システムに送られる沸騰水型原子炉システムの出力制限方法であって、
前記炉心の縦方向真上の前記炉心シュラウド内の位置における復水を解放するために、前記第1の復水器システムおよび前記第2の非常用復水器システムからの復水を、前記炉心シュラウドの上部プレナムまたは煙突領域の一方または両者に戻すステップを含む、沸騰水型原子炉システムの出力制限方法。 - 前記戻すステップは、前記炉心シュラウド内の前記復水を戻し、また、前記下降管領域内の復水を戻す分岐部を含む復水戻りラインを介して、前記第2の非常用復水器システムから前記復水を戻す、請求項10に記載の方法。
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Application Number | Priority Date | Filing Date | Title |
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US16/381,147 US11139087B2 (en) | 2019-04-11 | 2019-04-11 | Use of isolation condenser and/or feedwater to limit core flow, core power, and pressure in a boiling water reactor |
US16/381,147 | 2019-04-11 | ||
PCT/US2020/024146 WO2020210010A1 (en) | 2019-04-11 | 2020-03-23 | Use of isolation condenser and/or feedwater to limit core flow, core power, and pressure in a boiling water reactor |
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JP2022528179A JP2022528179A (ja) | 2022-06-08 |
JP7443394B2 true JP7443394B2 (ja) | 2024-03-05 |
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EP (1) | EP3953945A1 (ja) |
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JP2020165660A (ja) | 2019-03-28 | 2020-10-08 | 日立Geニュークリア・エナジー株式会社 | Atws対策設備やそれを備えた自然循環型沸騰水型原子炉 |
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US3625817A (en) * | 1968-05-29 | 1971-12-07 | James H Anderson | Binary power cycle for nuclear power plants |
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SE414683B (sv) * | 1977-05-16 | 1980-08-11 | Asea Atom Ab | Kokarvattenreaktor |
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US4810460A (en) | 1988-02-22 | 1989-03-07 | General Electric Company | Nuclear boiling water reactor upper plenum with lateral throughpipes |
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JP2835120B2 (ja) * | 1990-01-25 | 1998-12-14 | 株式会社東芝 | 自然循環式沸騰水型原子炉 |
JP2965312B2 (ja) * | 1990-02-23 | 1999-10-18 | 株式会社日立製作所 | 非常用復水器系 |
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JP5876320B2 (ja) * | 2012-02-23 | 2016-03-02 | 日立Geニュークリア・エナジー株式会社 | 原子力プラント |
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