AR036372A1 - PROCEDURE FOR DECREASING CORROSION EROSION IN PUMP DUCTS PROVIDED IN THE PRIMARY CIRCUIT OF A NUCLEAR POWER PLANT OF CANDU TYPE. - Google Patents

PROCEDURE FOR DECREASING CORROSION EROSION IN PUMP DUCTS PROVIDED IN THE PRIMARY CIRCUIT OF A NUCLEAR POWER PLANT OF CANDU TYPE.

Info

Publication number
AR036372A1
AR036372A1 ARP020103227A ARP020103227A AR036372A1 AR 036372 A1 AR036372 A1 AR 036372A1 AR P020103227 A ARP020103227 A AR P020103227A AR P020103227 A ARP020103227 A AR P020103227A AR 036372 A1 AR036372 A1 AR 036372A1
Authority
AR
Argentina
Prior art keywords
power plant
nuclear power
primary circuit
procedure
ducts provided
Prior art date
Application number
ARP020103227A
Other languages
Spanish (es)
Inventor
Georg Kraemer
Franz Ammann
Klaus Streit
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 AR036372A1 publication Critical patent/AR036372A1/en

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

Abstract

Procedimiento para disminuir la erosión por corrosión en conductos de empalme (12S, 12b) dispuestos en el circuito primario de una central nuclear del tipo CANDU. De acuerdo con la presente, para ello se disminuye la rugosidad superficial producida durante la operación de la central nuclear por el depósito de productos de corrosión en la pared interna del lado primario de los tubos del intercambiador de calor (22) de un generador de vapor (20) dispuesto en el circuito primario mediante el tratamiento con un medio aplicado a chorro.Procedure to reduce erosion by corrosion in junction conduits (12S, 12b) arranged in the primary circuit of a nuclear power plant of the CANDU type. Accordingly, the surface roughness produced during the operation of the nuclear power plant is reduced by the deposit of corrosion products on the inner wall of the primary side of the heat exchanger tubes (22) of a steam generator (20) arranged in the primary circuit by treatment with a jet applied medium.

ARP020103227A 2001-08-28 2002-08-28 PROCEDURE FOR DECREASING CORROSION EROSION IN PUMP DUCTS PROVIDED IN THE PRIMARY CIRCUIT OF A NUCLEAR POWER PLANT OF CANDU TYPE. AR036372A1 (en)

Applications Claiming Priority (1)

Application Number Priority Date Filing Date Title
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 (1)

Publication Number Publication Date
AR036372A1 true AR036372A1 (en) 2004-09-01

Family

ID=7696337

Family Applications (1)

Application Number Title Priority Date Filing Date
ARP020103227A AR036372A1 (en) 2001-08-28 2002-08-28 PROCEDURE FOR DECREASING CORROSION EROSION IN PUMP DUCTS PROVIDED IN THE PRIMARY CIRCUIT OF A NUCLEAR POWER PLANT OF CANDU TYPE.

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)

Families Citing this family (6)

* 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
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

Family Cites Families (6)

* Cited by examiner, † Cited by third party
Publication number Priority date Publication date Assignee Title
EP0027388B1 (en) * 1979-10-16 1983-05-11 Westinghouse Electric Corporation Decontamination method and apparatus
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

Also Published As

Publication number Publication date
KR100589829B1 (en) 2006-06-14
DE10141304A1 (en) 2003-03-20
CA2393461A1 (en) 2002-10-27
RO121098B1 (en) 2006-12-29
KR20030019126A (en) 2003-03-06
CN1263978C (en) 2006-07-12
CA2393461C (en) 2003-12-23
CN1401932A (en) 2003-03-12

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Legal Events

Date Code Title Description
FG Grant, registration
FD Application declared void or lapsed, e.g., due to non-payment of fee