JP2019095450A - 原子力発電所 - Google Patents
原子力発電所 Download PDFInfo
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- JP2019095450A JP2019095450A JP2018219118A JP2018219118A JP2019095450A JP 2019095450 A JP2019095450 A JP 2019095450A JP 2018219118 A JP2018219118 A JP 2018219118A JP 2018219118 A JP2018219118 A JP 2018219118A JP 2019095450 A JP2019095450 A JP 2019095450A
- Authority
- JP
- Japan
- Prior art keywords
- steam
- power plant
- steam generator
- coolant
- nuclear power
- Prior art date
- Legal status (The legal status is an assumption and is not a legal conclusion. Google has not performed a legal analysis and makes no representation as to the accuracy of the status listed.)
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Classifications
-
- 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
-
- F—MECHANICAL ENGINEERING; LIGHTING; HEATING; WEAPONS; BLASTING
- F22—STEAM GENERATION
- F22B—METHODS OF STEAM GENERATION; STEAM BOILERS
- F22B1/00—Methods of steam generation characterised by form of heating method
- F22B1/02—Methods of steam generation characterised by form of heating method by exploitation of the heat content of hot heat carriers
- F22B1/023—Methods of steam generation characterised by form of heating method by exploitation of the heat content of hot heat carriers with heating tubes, for nuclear reactors as far as they are not classified, according to a specified heating fluid, in another group
-
- F—MECHANICAL ENGINEERING; LIGHTING; HEATING; WEAPONS; BLASTING
- F22—STEAM GENERATION
- F22B—METHODS OF STEAM GENERATION; STEAM BOILERS
- F22B1/00—Methods of steam generation characterised by form of heating method
- F22B1/02—Methods of steam generation characterised by form of heating method by exploitation of the heat content of hot heat carriers
- F22B1/08—Methods of steam generation characterised by form of heating method by exploitation of the heat content of hot heat carriers the heat carrier being steam
- F22B1/12—Methods of steam generation characterised by form of heating method by exploitation of the heat content of hot heat carriers the heat carrier being steam produced by an indirect cyclic process
- F22B1/123—Steam generators downstream of a nuclear boiling water reactor
-
- F—MECHANICAL ENGINEERING; LIGHTING; HEATING; WEAPONS; BLASTING
- F22—STEAM GENERATION
- F22B—METHODS OF STEAM GENERATION; STEAM BOILERS
- F22B35/00—Control systems for steam boilers
- F22B35/004—Control systems for steam generators of nuclear power plants
-
- 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
-
- 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
-
- G—PHYSICS
- G21—NUCLEAR PHYSICS; NUCLEAR ENGINEERING
- G21D—NUCLEAR POWER PLANT
- G21D3/00—Control of nuclear power plant
- G21D3/04—Safety arrangements
-
- 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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- Engineering & Computer Science (AREA)
- Physics & Mathematics (AREA)
- General Engineering & Computer Science (AREA)
- High Energy & Nuclear Physics (AREA)
- Thermal Sciences (AREA)
- Mechanical Engineering (AREA)
- Plasma & Fusion (AREA)
- Life Sciences & Earth Sciences (AREA)
- Sustainable Development (AREA)
- Sustainable Energy (AREA)
- Emergency Management (AREA)
- Business, Economics & Management (AREA)
- Chemical & Material Sciences (AREA)
- Combustion & Propulsion (AREA)
- Structure Of Emergency Protection For Nuclear Reactors (AREA)
Abstract
Description
Claims (15)
- 原子力発電所であって、
原子炉圧力容器と、
前記原子炉圧力容器内で発生した熱エネルギーを利用して蒸気を発生させるように配置された蒸気発生器と、
前記原子炉圧力容器から前記蒸気発生器に熱エネルギーを伝達するための流体回路と、
緊急時において重力下で前記蒸気発生器に供給するための冷却液を貯蔵する冷却液タンクとを備え、
前記蒸気発生器は、蒸気を乾燥させるように構成された1つ以上の気水分離器を含む蒸気乾燥ゾーンを含み、
前記蒸気発生器および冷却液タンクは、緊急時において冷却液が前記冷却液タンクから前記蒸気発生器に供給されたときに、前記冷却液が前記蒸気乾燥ゾーンによって規定された閾値未満に留まるように構成されている、原子力発電所。 - 前記冷却水が前記閾値未満に留まっていることを条件に、前記または各気水分離器が前記蒸気発生器内の蒸気を乾燥させるように機能するように、前記閾値が設定されている、請求項1に記載の原子力発電所。
- 前記閾値は、前記蒸気乾燥ゾーンの下端によって規定されている、請求項1または2に記載の原子力発電所。
- 前記または各気水分離器は、少なくとも部分的に前記蒸気乾燥ゾーン内に位置する、請求項1乃至3のいずれか一項に記載の原子力発電所。
- 前記冷却液タンクは、冷却液を収容している、請求項1乃至4のいずれか一項に記載の原子力発電所。
- 前記冷却液タンク内の前記冷却液のレベルが前記閾値以下である、請求項5に記載の原子力発電所。
- 前記冷却液タンクは、原子炉格納容器の内側に設置されている、請求項1乃至6のいずれか一項に記載の原子力発電所。
- 前記冷却液タンクは、前記蒸気発生器の周囲を取り囲んでいる、請求項1乃至7のいずれか一項に記載の原子力発電所。
- 前記冷却液タンクは、前記冷却液タンクとその外側との間の流体連通を提供することができるバルブを有する、請求項1乃至8のいずれか一項に記載の原子力発電所。
- 前記蒸気発生器内の圧力を低下させることができる減圧バルブを更に備える、請求項1乃至9のいずれか一項に記載の原子力発電所。
- 前記減圧バルブは、蒸気を補助的な場所に送ることができる、請求項10に記載の原子力発電所。
- 前記冷却液が前記蒸気乾燥ゾーンによって規定された閾値未満のまま、重力下で前記冷却液タンクから前記蒸気発生器に冷却液を供給する工程を備える、請求項1乃至11のいずれか一項に記載の原子力発電所を運転する方法。
- 前記冷却液タンクとその外側との間に流体連通を提供するようにバルブを開く工程を更に備える、請求項12に記載の方法。
- 前記蒸気発生器内の圧力を低下させるように減圧バルブを開く工程を更に備える、請求項12または13に記載の方法。
- 前記減圧バルブを開く工程は、蒸気を補助的な場所に送る、請求項14に記載の方法。
Applications Claiming Priority (2)
Application Number | Priority Date | Filing Date | Title |
---|---|---|---|
GB1719431.7 | 2017-11-23 | ||
GB1719431.7A GB2568692B (en) | 2017-11-23 | 2017-11-23 | Nuclear power plants |
Publications (2)
Publication Number | Publication Date |
---|---|
JP2019095450A true JP2019095450A (ja) | 2019-06-20 |
JP7199634B2 JP7199634B2 (ja) | 2023-01-06 |
Family
ID=60950601
Family Applications (1)
Application Number | Title | Priority Date | Filing Date |
---|---|---|---|
JP2018219118A Active JP7199634B2 (ja) | 2017-11-23 | 2018-11-22 | 原子力発電所 |
Country Status (7)
Country | Link |
---|---|
US (1) | US20190164654A1 (ja) |
EP (1) | EP3492811B1 (ja) |
JP (1) | JP7199634B2 (ja) |
CA (1) | CA3025119A1 (ja) |
GB (1) | GB2568692B (ja) |
HU (1) | HUE062215T2 (ja) |
PL (1) | PL3492811T3 (ja) |
Families Citing this family (2)
Publication number | Priority date | Publication date | Assignee | Title |
---|---|---|---|---|
KR102574058B1 (ko) * | 2021-03-04 | 2023-09-04 | 한국원자력연구원 | 원자로의 피동무한냉각 구조체 및 그 작동방법 |
DE102022115375A1 (de) * | 2022-06-21 | 2023-12-21 | Franz Hofele | Wärmekraftwerk und Verfahren zur Kühlung eines Wärmekraftwerks |
Citations (6)
Publication number | Priority date | Publication date | Assignee | Title |
---|---|---|---|---|
JPS5052496A (ja) * | 1973-03-30 | 1975-05-09 | ||
US4239596A (en) * | 1977-12-16 | 1980-12-16 | Combustion Engineering, Inc. | Passive residual heat removal system for nuclear power plant |
JPS60254000A (ja) * | 1984-04-05 | 1985-12-14 | ウエスチングハウス エレクトリック コ−ポレ−ション | 蒸気発生器用緊急給水設備 |
JPS628094A (ja) * | 1985-07-01 | 1987-01-16 | フラマト−ム | 加圧水型原子炉用の自動調整緊急冷却装置 |
JPH04109197A (ja) * | 1989-09-19 | 1992-04-10 | Mitsubishi Heavy Ind Ltd | 加圧水型原子炉の炉心崩壊熱除去装置 |
JP2009210157A (ja) * | 2008-02-29 | 2009-09-17 | Mitsubishi Heavy Ind Ltd | 蒸気発生器 |
Family Cites Families (6)
Publication number | Priority date | Publication date | Assignee | Title |
---|---|---|---|---|
US4261298A (en) * | 1978-06-07 | 1981-04-14 | The Babcock & Wilcox Company | Vapor generating technique |
GB8817394D0 (en) * | 1988-07-21 | 1989-07-05 | Rolls Royce & Ass | Full pressure passive emergency core cooling and residual heat removal system for water cooled nuclear reactors |
DE4126630A1 (de) * | 1991-08-12 | 1993-02-18 | Siemens Ag | Sekundaerseitiges nachwaermeabfuhrsystem fuer druckwasser-kernreaktoren |
US9779840B2 (en) * | 2013-10-28 | 2017-10-03 | Bwxt Mpower, Inc. | PWR decay heat removal system in which steam from the pressurizer drives a turbine which drives a pump to inject water into the reactor pressure vessel |
CN104361913A (zh) * | 2014-11-19 | 2015-02-18 | 中科华核电技术研究院有限公司 | 二次侧非能动余热导出系统 |
GB2550352A (en) * | 2016-05-16 | 2017-11-22 | Rolls-Royce Power Eng Ltd | Power plant |
-
2017
- 2017-11-23 GB GB1719431.7A patent/GB2568692B/en active Active
-
2018
- 2018-11-08 US US16/184,606 patent/US20190164654A1/en not_active Abandoned
- 2018-11-09 HU HUE18205298A patent/HUE062215T2/hu unknown
- 2018-11-09 EP EP18205298.5A patent/EP3492811B1/en active Active
- 2018-11-09 PL PL18205298.5T patent/PL3492811T3/pl unknown
- 2018-11-22 JP JP2018219118A patent/JP7199634B2/ja active Active
- 2018-11-23 CA CA3025119A patent/CA3025119A1/en active Pending
Patent Citations (6)
Publication number | Priority date | Publication date | Assignee | Title |
---|---|---|---|---|
JPS5052496A (ja) * | 1973-03-30 | 1975-05-09 | ||
US4239596A (en) * | 1977-12-16 | 1980-12-16 | Combustion Engineering, Inc. | Passive residual heat removal system for nuclear power plant |
JPS60254000A (ja) * | 1984-04-05 | 1985-12-14 | ウエスチングハウス エレクトリック コ−ポレ−ション | 蒸気発生器用緊急給水設備 |
JPS628094A (ja) * | 1985-07-01 | 1987-01-16 | フラマト−ム | 加圧水型原子炉用の自動調整緊急冷却装置 |
JPH04109197A (ja) * | 1989-09-19 | 1992-04-10 | Mitsubishi Heavy Ind Ltd | 加圧水型原子炉の炉心崩壊熱除去装置 |
JP2009210157A (ja) * | 2008-02-29 | 2009-09-17 | Mitsubishi Heavy Ind Ltd | 蒸気発生器 |
Also Published As
Publication number | Publication date |
---|---|
CA3025119A1 (en) | 2019-05-23 |
US20190164654A1 (en) | 2019-05-30 |
JP7199634B2 (ja) | 2023-01-06 |
HUE062215T2 (hu) | 2023-10-28 |
GB2568692B (en) | 2020-01-22 |
EP3492811B1 (en) | 2023-04-26 |
PL3492811T3 (pl) | 2023-09-11 |
GB2568692A (en) | 2019-05-29 |
EP3492811A1 (en) | 2019-06-05 |
GB201719431D0 (en) | 2018-01-10 |
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