ZA947121B - Process for dismantling a worn steam generator of a pressurized water nuclear reactor - Google Patents

Process for dismantling a worn steam generator of a pressurized water nuclear reactor

Info

Publication number
ZA947121B
ZA947121B ZA947121A ZA947121A ZA947121B ZA 947121 B ZA947121 B ZA 947121B ZA 947121 A ZA947121 A ZA 947121A ZA 947121 A ZA947121 A ZA 947121A ZA 947121 B ZA947121 B ZA 947121B
Authority
ZA
South Africa
Prior art keywords
dismantling
steam generator
nuclear reactor
pressurized water
water nuclear
Prior art date
Application number
ZA947121A
Other languages
English (en)
Inventor
Michel Dubourg
Original Assignee
Framatome Sa
Priority date (The priority date 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 date listed.)
Filing date
Publication date
Application filed by Framatome Sa filed Critical Framatome Sa
Publication of ZA947121B publication Critical patent/ZA947121B/xx

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)
ZA947121A 1993-09-16 1994-09-15 Process for dismantling a worn steam generator of a pressurized water nuclear reactor ZA947121B (en)

Applications Claiming Priority (1)

Application Number Priority Date Filing Date Title
FR9311055A FR2710182B1 (fr) 1993-09-16 1993-09-16 Procédé de démantèlement d'un générateur de vapeur usagé d'un réacteur nucléaire à eau sous pression.

Publications (1)

Publication Number Publication Date
ZA947121B true ZA947121B (en) 1996-03-15

Family

ID=9450941

Family Applications (1)

Application Number Title Priority Date Filing Date
ZA947121A ZA947121B (en) 1993-09-16 1994-09-15 Process for dismantling a worn steam generator of a pressurized water nuclear reactor

Country Status (7)

Country Link
EP (1) EP0719441A1 (OSRAM)
KR (1) KR960705326A (OSRAM)
AU (1) AU7540194A (OSRAM)
FR (1) FR2710182B1 (OSRAM)
TW (1) TW247364B (OSRAM)
WO (1) WO1995008173A1 (OSRAM)
ZA (1) ZA947121B (OSRAM)

Families Citing this family (4)

* Cited by examiner, † Cited by third party
Publication number Priority date Publication date Assignee Title
FR2853129B1 (fr) * 2003-03-28 2005-09-09 Salvarem Procede et produit de decontamination radioactive
FR2917154B1 (fr) * 2007-06-06 2009-10-02 Areva Np Sas Procede de demantelement pour la reutilisation des elements de l'enveloppe de pression d'un generateur de vapeur usage d'une centrale nucleaire.
CN106369886B (zh) * 2016-11-07 2022-07-08 珠海格力电器股份有限公司 干式蒸发器
JP7313306B2 (ja) * 2020-03-26 2023-07-24 株式会社神戸製鋼所 熱交換器の解体方法

Family Cites Families (6)

* Cited by examiner, † Cited by third party
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 (de) * 1983-08-31 1985-03-14 Siempelkamp Gießerei GmbH & Co, 4150 Krefeld Anlage fuer rueckgewinnung metallischer komponenten von kernkraftwerken
DE3404106C2 (de) * 1984-02-07 1986-10-02 Siempelkamp Gießerei GmbH & Co, 4150 Krefeld Ofenanlage zum Aufschmelzen metallischer Komponenten von Kernkraftwerken
SE465142B (sv) * 1988-08-11 1991-07-29 Studsvik Ab Foerfarande foer dekontaminering av korrosionsprodukter i kaernkraftsreaktorer
FR2687005B1 (fr) * 1992-02-03 1994-10-21 Framatome Sa Procede et installation de decontamination de la partie primaire d'un generateur de vapeur usage d'un reacteur nucleaire a eau ordinaire sous pression.

Also Published As

Publication number Publication date
WO1995008173A1 (fr) 1995-03-23
FR2710182A1 (fr) 1995-03-24
KR960705326A (ko) 1996-10-09
EP0719441A1 (fr) 1996-07-03
FR2710182B1 (fr) 1995-12-08
TW247364B (OSRAM) 1995-05-11
AU7540194A (en) 1995-04-03

Similar Documents

Publication Publication Date Title
EP0232186A3 (en) Passive safety system for a pressurized water nuclear reactor
GB2147452B (en) A fuel assembly for a pressurized water nuclear reactor
ZA873077B (en) Process and device for remotely lining a steam generator tube of a pressurized water nuclear reactor
CS192591A3 (en) Process and apparatus for dismantling irradiated section of a nuclear reactor
ZA898639B (en) Method of controlling a pressurized water nuclear reactor and a nuclear reactor implementing same
FR2614462B1 (fr) Procede de remplacement integral d'un generateur de vapeur d'un reacteur nucleaire a eau sous pression
DE3570118D1 (en) Method and apparatus for removal of residual sludge from a nuclear steam generator
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
DE3566591D1 (en) Decontamination of pressurized water reactors
DE3269951D1 (en) Apparatus for carrying out inspectionwork on a steam generator in a nuclear reactor and a method for insersting this apparatus in the chamber of a steam generator
DE3573304D1 (en) Emergency feedwater system for steam generators of a nuclear power plant
GB2161643B (en) Steam generator recirculating system for a pressurized water nuclear reactor
DE69405035D1 (de) System zum Druckabbau in einem Sicherheitsbehälter eines Druckwasserkernreaktors
NZ229992A (en) Shut-down process for a reactor and a reactor therefor
EP0416756A3 (en) Method for decontaminating a pressurized water nuclear reactor system
ZA947121B (en) Process for dismantling a worn steam generator of a pressurized water nuclear reactor
DE3474877D1 (en) Method for decontamination of a nuclear steam generator
EP0299539A3 (en) Apparatus for sleeving damaged tubes of a nuclear steam generator
ZA886297B (en) A method of protecting a pressurized water nuclear reactor against failures in its emergency stop means
HUT66988A (en) Method and apparatus for decontamination of promer part of a broke steam generator of with pressurized light water working reactor
ES551083A0 (es) Un generador de vapor para un reactor nuclear de agua presurizada
DE3164942D1 (en) Process for controlling the power delivered by a pressurized water nuclear reactor to a steam turbine
PL313815A1 (en) Matched steam-and-gas circulation system for a power plant with a pressure-type fluidised bed boiler as well as method of operating such system
DE3461117D1 (en) Steam generator for a liquid metal-cooled nuclear reactor
DE3160354D1 (en) Primary circuit pressure-control method during the shut-down period of a pressurised water nuclear reactor