ES8402451A1 - Feedwater nozzle leakage monitoring device for reactor - Google Patents

Feedwater nozzle leakage monitoring device for reactor

Info

Publication number
ES8402451A1
ES8402451A1 ES512497A ES512497A ES8402451A1 ES 8402451 A1 ES8402451 A1 ES 8402451A1 ES 512497 A ES512497 A ES 512497A ES 512497 A ES512497 A ES 512497A ES 8402451 A1 ES8402451 A1 ES 8402451A1
Authority
ES
Spain
Prior art keywords
temperature
leakage
reactor
monitoring device
fluid
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.)
Expired
Application number
ES512497A
Other languages
Spanish (es)
Other versions
ES512497A0 (en
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.)
General Electric Co
Original Assignee
General Electric Co
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 General Electric Co filed Critical General Electric Co
Publication of ES8402451A1 publication Critical patent/ES8402451A1/en
Publication of ES512497A0 publication Critical patent/ES512497A0/en
Granted legal-status Critical Current

Links

Classifications

    • G—PHYSICS
    • G01—MEASURING; TESTING
    • G01M—TESTING STATIC OR DYNAMIC BALANCE OF MACHINES OR STRUCTURES; TESTING OF STRUCTURES OR APPARATUS, NOT OTHERWISE PROVIDED FOR
    • G01M3/00—Investigating fluid-tightness of structures
    • G01M3/002—Investigating fluid-tightness of structures by using thermal means
    • G—PHYSICS
    • G21—NUCLEAR PHYSICS; NUCLEAR ENGINEERING
    • G21C—NUCLEAR REACTORS
    • G21C13/00—Pressure vessels; Containment vessels; Containment in general
    • G21C13/02—Details
    • G21C13/032—Joints between tubes and vessel walls, e.g. taking into account thermal stresses
    • G—PHYSICS
    • G21—NUCLEAR PHYSICS; NUCLEAR ENGINEERING
    • G21C—NUCLEAR REACTORS
    • G21C17/00—Monitoring; Testing ; Maintaining
    • G21C17/002—Detection of leaks
    • 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

  • Physics & Mathematics (AREA)
  • Engineering & Computer Science (AREA)
  • Plasma & Fusion (AREA)
  • General Engineering & Computer Science (AREA)
  • High Energy & Nuclear Physics (AREA)
  • General Physics & Mathematics (AREA)
  • Monitoring And Testing Of Nuclear Reactors (AREA)
  • Examining Or Testing Airtightness (AREA)
  • Investigating Or Analyzing Materials Using Thermal Means (AREA)

Abstract

In an arrangement for feeding a fluid at a specific temperature into a container (20), containing a fluid at a distinctly different temperature, from an inlet pipe (52) via an inlet nozzle (54), provision is made of an exchangeable thermal bushing (56). An excessive amount of leakage of the feed fluid at the connecting point between the upstream end of the thermal bushing (56) and the inlet nozzle (54) can cause thermal cycling of the inner surface of the nozzle and, as a consequence, formation of cracks therein. According to the invention, the rate of flow of leakage is monitored by measuring the temperature of the outside of the inlet nozzle (54) and determining the relationship between this temperature and the rate of flow of leakage.
ES512497A 1981-05-29 1982-05-24 A DEVICE TO DETERMINE THE LEAK FLOW RATE OF THE INLET FLUID IN A NUCLEAR REACTOR. Granted ES512497A0 (en)

Applications Claiming Priority (1)

Application Number Priority Date Filing Date Title
US26827081A 1981-05-29 1981-05-29

Publications (2)

Publication Number Publication Date
ES8402451A1 true ES8402451A1 (en) 1984-01-16
ES512497A0 ES512497A0 (en) 1984-01-16

Family

ID=23022210

Family Applications (1)

Application Number Title Priority Date Filing Date
ES512497A Granted ES512497A0 (en) 1981-05-29 1982-05-24 A DEVICE TO DETERMINE THE LEAK FLOW RATE OF THE INLET FLUID IN A NUCLEAR REACTOR.

Country Status (5)

Country Link
JP (1) JPS6018035B2 (en)
DE (1) DE3219512A1 (en)
ES (1) ES512497A0 (en)
IT (1) IT1190841B (en)
SE (1) SE8203336L (en)

Families Citing this family (2)

* Cited by examiner, † Cited by third party
Publication number Priority date Publication date Assignee Title
DE4039176C2 (en) * 1990-12-06 1996-04-11 Ver Energiewerke Ag Procedure for determining and evaluating damaged pipes in a pipe system
US7421915B2 (en) * 2006-03-24 2008-09-09 The Tokyo Electric Power Company, Incorporated Nondestructive inspection apparatus

Family Cites Families (2)

* Cited by examiner, † Cited by third party
Publication number Priority date Publication date Assignee Title
DE2742396C2 (en) * 1977-09-21 1982-04-22 Kernforschungszentrum Karlsruhe Gmbh, 7500 Karlsruhe Method and circuit arrangements for detecting a cooling fault
US4168071A (en) * 1978-03-17 1979-09-18 General Electric Company Thermal isolator

Also Published As

Publication number Publication date
JPS57207892A (en) 1982-12-20
SE8203336L (en) 1982-11-30
IT8221534A0 (en) 1982-05-28
ES512497A0 (en) 1984-01-16
JPS6018035B2 (en) 1985-05-08
DE3219512A1 (en) 1982-12-23
IT1190841B (en) 1988-02-24

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