JPS6186677A - 原子炉用圧力容器の安全を高める方法と装置 - Google Patents
原子炉用圧力容器の安全を高める方法と装置Info
- Publication number
- JPS6186677A JPS6186677A JP60205191A JP20519185A JPS6186677A JP S6186677 A JPS6186677 A JP S6186677A JP 60205191 A JP60205191 A JP 60205191A JP 20519185 A JP20519185 A JP 20519185A JP S6186677 A JPS6186677 A JP S6186677A
- Authority
- JP
- Japan
- Prior art keywords
- gas
- pressure vessel
- pressure
- cooling gas
- prestressed concrete
- 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.)
- Granted
Links
- 238000000034 method Methods 0.000 title claims description 16
- 239000000112 cooling gas Substances 0.000 claims description 59
- 239000007789 gas Substances 0.000 claims description 31
- 239000011513 prestressed concrete Substances 0.000 claims description 16
- 238000004140 cleaning Methods 0.000 claims description 10
- 230000009471 action Effects 0.000 claims description 8
- 238000001816 cooling Methods 0.000 claims description 8
- 230000000694 effects Effects 0.000 claims description 6
- 238000010992 reflux Methods 0.000 claims description 5
- OKTJSMMVPCPJKN-UHFFFAOYSA-N Carbon Chemical compound [C] OKTJSMMVPCPJKN-UHFFFAOYSA-N 0.000 claims description 3
- 229910002804 graphite Inorganic materials 0.000 claims description 3
- 239000010439 graphite Substances 0.000 claims description 3
- 230000009172 bursting Effects 0.000 claims description 2
- 229910000831 Steel Inorganic materials 0.000 claims 1
- 239000011248 coating agent Substances 0.000 claims 1
- 238000000576 coating method Methods 0.000 claims 1
- 238000005338 heat storage Methods 0.000 claims 1
- 230000002265 prevention Effects 0.000 claims 1
- 239000010959 steel Substances 0.000 claims 1
- 238000011144 upstream manufacturing Methods 0.000 claims 1
- 230000004992 fission Effects 0.000 description 6
- 230000006378 damage Effects 0.000 description 5
- 239000001307 helium Substances 0.000 description 3
- 229910052734 helium Inorganic materials 0.000 description 3
- SWQJXJOGLNCZEY-UHFFFAOYSA-N helium atom Chemical compound [He] SWQJXJOGLNCZEY-UHFFFAOYSA-N 0.000 description 3
- 238000010586 diagram Methods 0.000 description 2
- 238000001914 filtration Methods 0.000 description 2
- 230000020169 heat generation Effects 0.000 description 2
- 230000009467 reduction Effects 0.000 description 2
- RYGMFSIKBFXOCR-UHFFFAOYSA-N Copper Chemical compound [Cu] RYGMFSIKBFXOCR-UHFFFAOYSA-N 0.000 description 1
- 208000027418 Wounds and injury Diseases 0.000 description 1
- 230000002159 abnormal effect Effects 0.000 description 1
- 230000004913 activation Effects 0.000 description 1
- 230000002411 adverse Effects 0.000 description 1
- 230000008901 benefit Effects 0.000 description 1
- 229910052802 copper Inorganic materials 0.000 description 1
- 239000010949 copper Substances 0.000 description 1
- 238000000151 deposition Methods 0.000 description 1
- 238000007599 discharging Methods 0.000 description 1
- 238000004146 energy storage Methods 0.000 description 1
- 238000005516 engineering process Methods 0.000 description 1
- 238000000605 extraction Methods 0.000 description 1
- 238000012681 fiber drawing Methods 0.000 description 1
- 208000014674 injury Diseases 0.000 description 1
- 238000009434 installation Methods 0.000 description 1
- 238000000197 pyrolysis Methods 0.000 description 1
- 230000005855 radiation Effects 0.000 description 1
- 230000002285 radioactive effect Effects 0.000 description 1
- 230000008439 repair process Effects 0.000 description 1
Classifications
-
- G—PHYSICS
- G21—NUCLEAR PHYSICS; NUCLEAR ENGINEERING
- G21C—NUCLEAR REACTORS
- G21C9/00—Emergency protection arrangements structurally associated with the reactor, e.g. safety valves provided with pressure equalisation devices
- G21C9/004—Pressure suppression
- G21C9/008—Pressure suppression by rupture-discs or -diaphragms
-
- 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
- Y10S376/90—Particular material or material shapes for fission reactors
- Y10S376/904—Moderator, reflector, or coolant materials
Landscapes
- 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)
Applications Claiming Priority (2)
| Application Number | Priority Date | Filing Date | Title |
|---|---|---|---|
| DE3435256.2 | 1984-09-26 | ||
| DE19843435256 DE3435256A1 (de) | 1984-09-26 | 1984-09-26 | Verfahren und einrichtung zur druckabsicherung eines von einem reaktorschutzgebaeude umgebenen spannbetondruckbehaelters und zur verhinderung von aktivitaetsfreisetzung an die umgebung |
Publications (2)
| Publication Number | Publication Date |
|---|---|
| JPS6186677A true JPS6186677A (ja) | 1986-05-02 |
| JPH0551114B2 JPH0551114B2 (en, 2012) | 1993-07-30 |
Family
ID=6246371
Family Applications (1)
| Application Number | Title | Priority Date | Filing Date |
|---|---|---|---|
| JP60205191A Granted JPS6186677A (ja) | 1984-09-26 | 1985-09-18 | 原子炉用圧力容器の安全を高める方法と装置 |
Country Status (3)
| Country | Link |
|---|---|
| US (1) | US4645641A (en, 2012) |
| JP (1) | JPS6186677A (en, 2012) |
| DE (1) | DE3435256A1 (en, 2012) |
Families Citing this family (18)
| Publication number | Priority date | Publication date | Assignee | Title |
|---|---|---|---|---|
| DE3526377A1 (de) * | 1985-07-24 | 1987-02-05 | Kernforschungsanlage Juelich | Kernreaktor, insbesondere hochtemperaturreaktor |
| DE3637795A1 (de) * | 1986-11-06 | 1988-05-11 | Siemens Ag | Kernkraftwerk mit einer sicherheitshuelle |
| DE3729501A1 (de) * | 1987-03-23 | 1988-10-06 | Siemens Ag | Verfahren und einrichtung zur druckentlastung eines kernkraftwerkes |
| US5108695A (en) * | 1991-02-25 | 1992-04-28 | Westinghouse Electric Corp. | Ventilating system for an emergency feedwater enclosure in a nuclear power plant |
| DE19531296C1 (de) * | 1995-08-25 | 1996-12-05 | Krantz Tkt Gmbh | Einrichtung zur Umrüstung eines in einem Abluftkanal eines Kernkraftwerks angeordneten Schwebstoffilters der Petrijanow-Bauart |
| DE19946286A1 (de) * | 1999-09-27 | 2001-04-19 | Forschungszentrum Juelich Gmbh | Reaktorzelle mit Vorrichtung zur Druckentlastung |
| DE60028164T2 (de) * | 1999-11-24 | 2007-05-10 | Kabushiki Kaisha Toshiba | Druckentlastungsvorrichtung für einen Kernreaktorbehälter |
| JP2004526157A (ja) * | 2001-03-26 | 2004-08-26 | ペブル ベッド モデュラー リアクター （プロプリエタリー）リミテッド | 原子力発電所を運転する方法および原子力発電所 |
| US9562646B2 (en) * | 2013-07-12 | 2017-02-07 | Ut-Battelle, Llc | Hydrogen storage container |
| CN105097060B (zh) * | 2015-08-24 | 2017-11-21 | 清华大学 | 一种高温气冷堆优化氦净化再生系统及再生方法 |
| JP7089826B2 (ja) * | 2016-09-20 | 2022-06-23 | コンティニューム ダイナミクス，インコーポレイテッド | Ｅｃｃｓストレイナ圧力ヘッド損失を軽減するために制御されたデブリを用いる原子炉 |
| US10706973B2 (en) | 2017-05-02 | 2020-07-07 | Ge-Hitachi Nuclear Energy Americas Llc | Very simplified boiling water reactors for commercial electricity generation |
| US10867712B2 (en) | 2017-06-28 | 2020-12-15 | Ge-Hitachi Nuclear Energy Americas Llc | Isolation condenser systems for nuclear reactor commercial electricity generation |
| US11380451B2 (en) * | 2017-08-15 | 2022-07-05 | Ge-Hitachi Nuclear Energy Americas Llc | Depressurization and coolant injection systems for very simplified boiling water reactors |
| JP6927893B2 (ja) * | 2018-01-18 | 2021-09-01 | 日立Ｇｅニュークリア・エナジー株式会社 | 原子炉格納容器ベントシステム |
| CN110534219B (zh) * | 2019-08-28 | 2020-12-29 | 清华大学 | 颗粒抽吸装置和方法 |
| CN110828004A (zh) * | 2019-12-06 | 2020-02-21 | 华能山东石岛湾核电有限公司 | 一种高温气冷堆试验用超压保护装置及其使用方法 |
| US11373769B2 (en) | 2019-12-24 | 2022-06-28 | Ge-Hitachi Nuclear Energy Americas Llc | Passive containment cooling system for a nuclear reactor |
Family Cites Families (4)
| Publication number | Priority date | Publication date | Assignee | Title |
|---|---|---|---|---|
| US3105028A (en) * | 1963-09-24 | Apparatus for removing contaminated coolant from reactor system | ||
| DE2057405A1 (de) * | 1970-11-21 | 1972-06-15 | Staebler Karl Dipl Ing | Notkondensationsanlage bei Bruch des Primaer-Kreislaufsystems allein oder bei zusaetzlichem Bruch der Sicherheitshuelle in einem Kernkraftwerk,dadurch gekennzeichnet,dass der Turbinenkondensator zur Kondensation der entweichenden Dampfwolke verwendet wird |
| DE2601460C2 (de) * | 1976-01-16 | 1985-05-15 | Hochtemperatur-Kernkraftwerk GmbH (HKG) Gemeinsames Europäisches Unternehmen, 4701 Uentrop | Verfahren zum Entfernen von Verunreinigungen aus dem Kühlgas von Hochtemperatur-Kernreaktoren |
| DE3212265C2 (de) * | 1982-04-02 | 1984-05-10 | Hochtemperatur-Reaktorbau GmbH, 5000 Köln | Verfahren und Einrichtung zur gezielten Aktivitätsableitung aus dem Reaktorschutzgebäude einer gasgekühlten Kernkraftanlage |
-
1984
- 1984-09-26 DE DE19843435256 patent/DE3435256A1/de active Granted
-
1985
- 1985-09-18 JP JP60205191A patent/JPS6186677A/ja active Granted
- 1985-09-26 US US06/780,272 patent/US4645641A/en not_active Expired - Fee Related
Also Published As
| Publication number | Publication date |
|---|---|
| US4645641A (en) | 1987-02-24 |
| DE3435256A1 (de) | 1986-04-03 |
| DE3435256C2 (en, 2012) | 1992-05-27 |
| JPH0551114B2 (en, 2012) | 1993-07-30 |
Similar Documents
| Publication | Publication Date | Title |
|---|---|---|
| JPS6186677A (ja) | 原子炉用圧力容器の安全を高める方法と装置 | |
| US6795518B1 (en) | Integral PWR with diverse emergency cooling and method of operating same | |
| CN103383865B (zh) | 用于核反应堆的被动应急给水系统 | |
| US4587079A (en) | System for the emergency cooling of a pressurized water nuclear reactor core | |
| US20210202121A1 (en) | Flow Mixing T-Unit of Reactor Volume Control System | |
| US11646123B2 (en) | Three-way valve operational to both transfer steam to a decontamination water tank under one accident situation and discharge the steam to atmosphere under a different accident situation | |
| US5085825A (en) | Standby safety injection system for nuclear reactor plants | |
| CN108831573A (zh) | 一种核电站二次侧非能动余热排出安全系统 | |
| JPS6138308A (ja) | 蒸気発生器の２次冷却材再循環装置 | |
| CN209149827U (zh) | 一种能动和非能动结合的二次侧余热排出系统 | |
| RU2150153C1 (ru) | Аварийная система питания и борирования для реактора, охлаждаемого водой под давлением, и способ эксплуатации такой аварийной системы питания и борирования | |
| JPH04109197A (ja) | 加圧水型原子炉の炉心崩壊熱除去装置 | |
| JPS61148388A (ja) | 原子炉装置 | |
| CN114360751B (zh) | 一种提升封闭管段可靠性的浮动堆安注系统 | |
| SU971015A1 (ru) | Система аварийного охлаждени активной зоны водо-вод ного реактора | |
| KR100448876B1 (ko) | 원자력발전소의 비상급수 시스템 | |
| JPH08146184A (ja) | 原子炉格納容器 | |
| Luckas et al. | Assessment of candidate accident management strategies | |
| CN111696689B (zh) | 一种安全注入系统及核电站 | |
| Yan et al. | Passive safety systems of advanced nuclear power plant: AP1000 | |
| Gros et al. | Use of probabilistic methods for the improvement of technical specifications | |
| JPS6117988A (ja) | 原子炉の安全装置 | |
| JPS6036995A (ja) | 主蒸気管漏洩検出装置 | |
| JPS6177799A (ja) | 可搬式の可燃性ガス濃度制御装置 | |
| Gouffon et al. | The risks and safety functions |