AU7540194A - Method of dismantling a worn steam generator in a pressurized water nuclear reactor - Google Patents
Method of dismantling a worn steam generator in a pressurized water nuclear reactorInfo
- Publication number
- AU7540194A AU7540194A AU75401/94A AU7540194A AU7540194A AU 7540194 A AU7540194 A AU 7540194A AU 75401/94 A AU75401/94 A AU 75401/94A AU 7540194 A AU7540194 A AU 7540194A AU 7540194 A AU7540194 A AU 7540194A
- Authority
- AU
- Australia
- Prior art keywords
- dismantling
- steam generator
- nuclear reactor
- pressurized water
- water nuclear
- 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.)
- Abandoned
Links
Classifications
-
- 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
- F22B37/007—Installation or removal of nuclear steam generators
-
- G—PHYSICS
- G21—NUCLEAR PHYSICS; NUCLEAR ENGINEERING
- G21D—NUCLEAR POWER PLANT
- G21D1/00—Details of nuclear power plant
- G21D1/003—Nuclear facilities decommissioning arrangements
-
- G—PHYSICS
- G21—NUCLEAR PHYSICS; NUCLEAR ENGINEERING
- G21F—PROTECTION AGAINST X-RADIATION, GAMMA RADIATION, CORPUSCULAR RADIATION OR PARTICLE BOMBARDMENT; TREATING RADIOACTIVELY CONTAMINATED MATERIAL; DECONTAMINATION ARRANGEMENTS THEREFOR
- G21F9/00—Treating radioactively contaminated material; Decontamination arrangements therefor
- G21F9/28—Treating solids
- G21F9/30—Processing
-
- 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
Landscapes
- Physics & Mathematics (AREA)
- Engineering & Computer Science (AREA)
- General Engineering & Computer Science (AREA)
- High Energy & Nuclear Physics (AREA)
- Thermal Sciences (AREA)
- Mechanical Engineering (AREA)
- Plasma & Fusion (AREA)
- Processing Of Solid Wastes (AREA)
Applications Claiming Priority (3)
Application Number | Priority Date | Filing Date | Title |
---|---|---|---|
FR9311055A FR2710182B1 (en) | 1993-09-16 | 1993-09-16 | Process for dismantling a used steam generator from a pressurized water nuclear reactor. |
FR9311055 | 1993-09-16 | ||
PCT/FR1994/001027 WO1995008173A1 (en) | 1993-09-16 | 1994-08-29 | Method of dismantling a worn steam generator in a pressurized water nuclear reactor |
Publications (1)
Publication Number | Publication Date |
---|---|
AU7540194A true AU7540194A (en) | 1995-04-03 |
Family
ID=9450941
Family Applications (1)
Application Number | Title | Priority Date | Filing Date |
---|---|---|---|
AU75401/94A Abandoned AU7540194A (en) | 1993-09-16 | 1994-08-29 | Method of dismantling a worn steam generator in a pressurized water nuclear reactor |
Country Status (7)
Country | Link |
---|---|
EP (1) | EP0719441A1 (en) |
KR (1) | KR960705326A (en) |
AU (1) | AU7540194A (en) |
FR (1) | FR2710182B1 (en) |
TW (1) | TW247364B (en) |
WO (1) | WO1995008173A1 (en) |
ZA (1) | ZA947121B (en) |
Families Citing this family (4)
Publication number | Priority date | Publication date | Assignee | Title |
---|---|---|---|---|
FR2853129B1 (en) * | 2003-03-28 | 2005-09-09 | Salvarem | METHOD AND PRODUCT FOR RADIOACTIVE DECONTAMINATION |
FR2917154B1 (en) * | 2007-06-06 | 2009-10-02 | Areva Np Sas | METHOD FOR DISMANTLING THE REUSE OF THE ELEMENTS OF THE PRESSURE ENVELOPE OF A STEAM GENERATOR USING A NUCLEAR POWER PLANT. |
CN106369886B (en) * | 2016-11-07 | 2022-07-08 | 珠海格力电器股份有限公司 | Dry evaporator |
JP7313306B2 (en) * | 2020-03-26 | 2023-07-24 | 株式会社神戸製鋼所 | Dismantling method of heat exchanger |
Family Cites Families (6)
Publication number | Priority date | Publication date | Assignee | Title |
---|---|---|---|---|
US4199857A (en) * | 1978-05-01 | 1980-04-29 | Westinghouse Electric Corp. | Tube bundle removal method and apparatus |
EP0043394A1 (en) * | 1980-07-02 | 1982-01-13 | Westinghouse Electric Corporation | Radiation shield ring assembly for disassembling components of a nuclear steam generator |
DE3331383A1 (en) * | 1983-08-31 | 1985-03-14 | Siempelkamp Gießerei GmbH & Co, 4150 Krefeld | PLANT FOR RECOVERY OF METALLIC COMPONENTS OF NUCLEAR POWER PLANTS |
DE3404106C2 (en) * | 1984-02-07 | 1986-10-02 | Siempelkamp Gießerei GmbH & Co, 4150 Krefeld | Furnace system for melting metallic components of nuclear power plants |
SE465142B (en) * | 1988-08-11 | 1991-07-29 | Studsvik Ab | PROCEDURES DISCONTINUATE CORROSION PRODUCTS IN NUCLEAR POWER REACTORS |
FR2687005B1 (en) * | 1992-02-03 | 1994-10-21 | Framatome Sa | PROCESS AND INSTALLATION FOR DECONTAMINATION OF THE PRIMARY PART OF A STEAM GENERATOR USING A NUCLEAR REACTOR WITH REGULAR WATER UNDER PRESSURE. |
-
1993
- 1993-09-16 FR FR9311055A patent/FR2710182B1/en not_active Expired - Fee Related
-
1994
- 1994-08-29 WO PCT/FR1994/001027 patent/WO1995008173A1/en not_active Application Discontinuation
- 1994-08-29 KR KR1019960701416A patent/KR960705326A/en not_active Application Discontinuation
- 1994-08-29 AU AU75401/94A patent/AU7540194A/en not_active Abandoned
- 1994-08-29 EP EP94925531A patent/EP0719441A1/en not_active Withdrawn
- 1994-09-15 ZA ZA947121A patent/ZA947121B/en unknown
- 1994-09-15 TW TW083108529A patent/TW247364B/zh active
Also Published As
Publication number | Publication date |
---|---|
FR2710182A1 (en) | 1995-03-24 |
ZA947121B (en) | 1996-03-15 |
KR960705326A (en) | 1996-10-09 |
TW247364B (en) | 1995-05-11 |
WO1995008173A1 (en) | 1995-03-23 |
EP0719441A1 (en) | 1996-07-03 |
FR2710182B1 (en) | 1995-12-08 |
Similar Documents
Publication | Publication Date | Title |
---|---|---|
ZA898639B (en) | Method of controlling a pressurized water nuclear reactor and a nuclear reactor implementing same | |
NZ309302A (en) | A method for integrating of steam reforming unit and co-generation power plant | |
EP0605156A3 (en) | Method of effecting start-up of a cold steam turbine system in a combined cycle plant. | |
PL314726A1 (en) | Method of generating a h2-rich gas | |
ZA895679B (en) | Instrumentation device for the core of a pressurized water nuclear reactor and process and device for with standing and for installing this instrumentation device | |
GB2264585B (en) | Pressurized water reactor plant | |
ZA873077B (en) | Process and device for remotely lining a steam generator tube of a pressurized water nuclear reactor | |
GB2298243B (en) | Method of operating a steam turbine | |
GB2161643B (en) | Steam generator recirculating system for a pressurized water nuclear reactor | |
GB2156957B (en) | Emergency feedwater system for steam generators of a nuclear power plant | |
ES471091A1 (en) | System and method for retubing a steam generator | |
AU7540194A (en) | Method of dismantling a worn steam generator in a pressurized water nuclear reactor | |
HUT66988A (en) | Method and apparatus for decontamination of promer part of a broke steam generator of with pressurized light water working reactor | |
DE3474877D1 (en) | Method for decontamination of a nuclear steam generator | |
ZA825953B (en) | Steam generator and a steam power plant including such a steam generator | |
AU5643394A (en) | A method for directly monitoring the concentrations of water treatment compositions in steam generating systems | |
EP0205900A3 (en) | Pressure control system for a pressurized water nuclear reactor plant | |
AU6690896A (en) | Nuclear reactor plant having containment isolation | |
GB2301475B (en) | Critical power enhancement system for a pressurized fuel channel type nuclear reactor using chf enhancement appendages | |
EP0622937A3 (en) | A method of rapidly assessing damage to outside loop plant. | |
EP0338769A3 (en) | Process for inhibiting corrosion in a pressurized water nuclear reactor | |
DE3563489D1 (en) | Pressurized water reactor plant comprising a pressurized pool | |
IL100228A0 (en) | Method and system for generating energy utilizing a bleve-reaction | |
DE59604331D1 (en) | SECURITY CONTAINER OF A NUCLEAR POWER PLANT | |
FR2561753B1 (en) | STEAM GENERATOR, IN PARTICULAR FOR A PRESSURIZED WATER NUCLEAR REACTOR |