CA2393461A1 - Method for reducing corrosion erosion in the feeder pipes used in the primary loop of a candu-type nuclear power plant - Google Patents

Method for reducing corrosion erosion in the feeder pipes used in the primary loop of a candu-type nuclear power plant Download PDF

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Publication number
CA2393461A1
CA2393461A1 CA002393461A CA2393461A CA2393461A1 CA 2393461 A1 CA2393461 A1 CA 2393461A1 CA 002393461 A CA002393461 A CA 002393461A CA 2393461 A CA2393461 A CA 2393461A CA 2393461 A1 CA2393461 A1 CA 2393461A1
Authority
CA
Canada
Prior art keywords
candu
power plant
nuclear power
primary loop
reducing corrosion
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
Application number
CA002393461A
Other languages
French (fr)
Other versions
CA2393461C (en
Inventor
Georg Kraemer
Franz Ammann
Klaus Streit
Current Assignee (The listed assignees may be inaccurate. Google has not performed a legal analysis and makes no representation or warranty as to the accuracy of the list.)
Areva GmbH
Original Assignee
Framatome ANP GmbH
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 ANP GmbH filed Critical Framatome ANP GmbH
Publication of CA2393461A1 publication Critical patent/CA2393461A1/en
Application granted granted Critical
Publication of CA2393461C publication Critical patent/CA2393461C/en
Anticipated expiration legal-status Critical
Expired - Fee Related legal-status Critical Current

Links

Classifications

    • G—PHYSICS
    • G21—NUCLEAR PHYSICS; NUCLEAR ENGINEERING
    • G21D—NUCLEAR POWER PLANT
    • G21D1/00—Details of nuclear power plant
    • G21D1/006—Details of nuclear power plant primary side of steam generators
    • F—MECHANICAL ENGINEERING; LIGHTING; HEATING; WEAPONS; BLASTING
    • F28—HEAT EXCHANGE IN GENERAL
    • F28F—DETAILS OF HEAT-EXCHANGE AND HEAT-TRANSFER APPARATUS, OF GENERAL APPLICATION
    • F28F19/00—Preventing the formation of deposits or corrosion, e.g. by using filters or scrapers
    • F—MECHANICAL ENGINEERING; LIGHTING; HEATING; WEAPONS; BLASTING
    • F28—HEAT EXCHANGE IN GENERAL
    • F28G—CLEANING OF INTERNAL OR EXTERNAL SURFACES OF HEAT-EXCHANGE OR HEAT-TRANSFER CONDUITS, e.g. WATER TUBES OR BOILERS
    • F28G1/00—Non-rotary, e.g. reciprocated, appliances
    • F28G1/12—Fluid-propelled scrapers, bullets, or like solid bodies
    • G—PHYSICS
    • G21—NUCLEAR PHYSICS; NUCLEAR ENGINEERING
    • G21C—NUCLEAR REACTORS
    • G21C19/00—Arrangements for treating, for handling, or for facilitating the handling of, fuel or other materials which are used within the reactor, e.g. within its pressure vessel
    • G21C19/28—Arrangements for introducing fluent material into the reactor core; Arrangements for removing fluent material from the reactor core
    • G21C19/30—Arrangements for introducing fluent material into the reactor core; Arrangements for removing fluent material from the reactor core with continuous purification of circulating fluent material, e.g. by extraction of fission products deterioration or corrosion products, impurities, e.g. by cold traps
    • G21C19/303—Arrangements for introducing fluent material into the reactor core; Arrangements for removing fluent material from the reactor core with continuous purification of circulating fluent material, e.g. by extraction of fission products deterioration or corrosion products, impurities, e.g. by cold traps specially adapted for gases
    • 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
    • G21F9/001—Decontamination of contaminated objects, apparatus, clothes, food; Preventing contamination thereof
    • 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
    • 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

Landscapes

  • Engineering & Computer Science (AREA)
  • Physics & Mathematics (AREA)
  • General Engineering & Computer Science (AREA)
  • High Energy & Nuclear Physics (AREA)
  • Plasma & Fusion (AREA)
  • Mechanical Engineering (AREA)
  • Combustion & Propulsion (AREA)
  • Chemical & Material Sciences (AREA)
  • Food Science & Technology (AREA)
  • Life Sciences & Earth Sciences (AREA)
  • Thermal Sciences (AREA)
  • Heat-Exchange Devices With Radiators And Conduit Assemblies (AREA)
  • Monitoring And Testing Of Nuclear Reactors (AREA)
  • Preventing Corrosion Or Incrustation Of Metals (AREA)
  • Jet Pumps And Other Pumps (AREA)
  • Pressure Welding/Diffusion-Bonding (AREA)

Abstract

The present invention relates to a method for reducing corrosion erosion in the feeder pipes (12a, b) used in the primary loop of a CANDU* type nuclear power plant. According to the present invention, to this end the surface roughness of the primary side inside walls of the heat exchanger tubes (22) of a steam generator (20) that is arranged in the primary loop, which is caused by operation of the nuclear power plant, is reduced by treatment with an abrasive.

*CANDU is a registered trade-mark of Atomic Energy of Canada Limited.
CA002393461A 2001-08-28 2002-07-15 Method for reducing corrosion erosion in the feeder pipes used in the primary loop of a candu-type nuclear power plant Expired - Fee Related CA2393461C (en)

Applications Claiming Priority (2)

Application Number Priority Date Filing Date Title
DE10141304.1 2001-08-28
DE10141304A DE10141304A1 (en) 2001-08-28 2001-08-28 Reduction of corrosion erosion, in feeder pipes within primary loop of nuclear power plant, involves reducing surface roughness of primary side inner walls of heat exchanger tubes of steam generator using adhesive

Publications (2)

Publication Number Publication Date
CA2393461A1 true CA2393461A1 (en) 2002-10-27
CA2393461C CA2393461C (en) 2003-12-23

Family

ID=7696337

Family Applications (1)

Application Number Title Priority Date Filing Date
CA002393461A Expired - Fee Related CA2393461C (en) 2001-08-28 2002-07-15 Method for reducing corrosion erosion in the feeder pipes used in the primary loop of a candu-type nuclear power plant

Country Status (6)

Country Link
KR (1) KR100589829B1 (en)
CN (1) CN1263978C (en)
AR (1) AR036372A1 (en)
CA (1) CA2393461C (en)
DE (1) DE10141304A1 (en)
RO (1) RO121098B1 (en)

Cited By (1)

* Cited by examiner, † Cited by third party
Publication number Priority date Publication date Assignee Title
CN115274150A (en) * 2022-08-05 2022-11-01 中国核动力研究设计院 Two-loop waste heat discharge system and method based on concentrated seawater cooling

Families Citing this family (5)

* Cited by examiner, † Cited by third party
Publication number Priority date Publication date Assignee Title
KR101406609B1 (en) * 2012-12-03 2014-06-11 한국수력원자력 주식회사 Pressurized heavy water reactor
CN106683720B (en) * 2017-01-13 2018-01-30 中国核动力研究设计院 A kind of shell-and-tube lead-containing alloy cooled reactor
CN108231220A (en) * 2018-01-12 2018-06-29 中国核动力研究设计院 A kind of pipe tube type pressurized water reactor system
CN108511091A (en) * 2018-05-10 2018-09-07 中国核动力研究设计院 A kind of pipe tube type pressurized water reactor system
CN110095011A (en) * 2019-05-10 2019-08-06 大唐鲁北发电有限责任公司 A kind of condenser cleaning internally-inlaid diamond dust spherical structure

Family Cites Families (6)

* Cited by examiner, † Cited by third party
Publication number Priority date Publication date Assignee Title
ES495960A0 (en) * 1979-10-16 1985-09-01 Westinghouse Electric Corp METHOD AND ITS CORRESPONDING APPARATUS FOR DECONTAMINATING TUBES IN A NUCLEAR STEAM GENERATOR
US4645542A (en) * 1984-04-26 1987-02-24 Anco Engineers, Inc. Method of pressure pulse cleaning the interior of heat exchanger tubes located within a pressure vessel such as a tube bundle heat exchanger, boiler, condenser or the like
DE3624119A1 (en) * 1986-07-17 1988-01-21 Rhein Westfael Elect Werk Ag DEVICE FOR SIMULATING THE OPERATION OF A PRESSURE WATER REACTOR SYSTEM
JPH04227487A (en) * 1990-05-18 1992-08-17 Westinghouse Electric Corp <We> Method of removing sludge and corrosion product
FR2694654B1 (en) * 1992-08-06 1994-11-04 Framatome Sa Method and device for machining the internal surface of a tubular part and in particular an adapter fixed to the cover of the vessel of a pressurized water nuclear reactor.
DE69718729D1 (en) * 1996-09-10 2003-03-06 Kyokuto Rubber Co Cleaning system for heat exchangers and method for cleaning a heat exchanger

Cited By (2)

* Cited by examiner, † Cited by third party
Publication number Priority date Publication date Assignee Title
CN115274150A (en) * 2022-08-05 2022-11-01 中国核动力研究设计院 Two-loop waste heat discharge system and method based on concentrated seawater cooling
CN115274150B (en) * 2022-08-05 2024-05-07 中国核动力研究设计院 Two-loop waste heat discharging system and method based on concentrated seawater cooling

Also Published As

Publication number Publication date
CN1401932A (en) 2003-03-12
KR20030019126A (en) 2003-03-06
DE10141304A1 (en) 2003-03-20
CA2393461C (en) 2003-12-23
KR100589829B1 (en) 2006-06-14
RO121098B1 (en) 2006-12-29
AR036372A1 (en) 2004-09-01
CN1263978C (en) 2006-07-12

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MKLA Lapsed

Effective date: 20190715