FR2301764A1 - Expansion joint for nuclear reactor - connecting a sheet metal liner of a heated pressure vessel to pipe passing into the vessel - Google Patents

Expansion joint for nuclear reactor - connecting a sheet metal liner of a heated pressure vessel to pipe passing into the vessel

Info

Publication number
FR2301764A1
FR2301764A1 FR7505350A FR7505350A FR2301764A1 FR 2301764 A1 FR2301764 A1 FR 2301764A1 FR 7505350 A FR7505350 A FR 7505350A FR 7505350 A FR7505350 A FR 7505350A FR 2301764 A1 FR2301764 A1 FR 2301764A1
Authority
FR
France
Prior art keywords
vessel
interior
nuclear reactor
orifice
pipe
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
FR7505350A
Other languages
French (fr)
Other versions
FR2301764B1 (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.)
Commissariat a lEnergie Atomique et aux Energies Alternatives CEA
Original Assignee
Commissariat a lEnergie Atomique CEA
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 Commissariat a lEnergie Atomique CEA filed Critical Commissariat a lEnergie Atomique CEA
Priority to FR7505350A priority Critical patent/FR2301764A1/en
Publication of FR2301764A1 publication Critical patent/FR2301764A1/en
Application granted granted Critical
Publication of FR2301764B1 publication Critical patent/FR2301764B1/fr
Granted legal-status Critical Current

Links

Classifications

    • G—PHYSICS
    • G21—NUCLEAR PHYSICS; NUCLEAR ENGINEERING
    • G21C—NUCLEAR REACTORS
    • G21C15/00—Cooling arrangements within the pressure vessel containing the core; Selection of specific coolants
    • G21C15/02—Arrangements or disposition of passages in which heat is transferred to the coolant; Coolant flow control devices
    • G21C15/14—Arrangements or disposition of passages in which heat is transferred to the coolant; Coolant flow control devices from headers; from joints in ducts
    • F—MECHANICAL ENGINEERING; LIGHTING; HEATING; WEAPONS; BLASTING
    • F16—ENGINEERING ELEMENTS AND UNITS; GENERAL MEASURES FOR PRODUCING AND MAINTAINING EFFECTIVE FUNCTIONING OF MACHINES OR INSTALLATIONS; THERMAL INSULATION IN GENERAL
    • F16L—PIPES; JOINTS OR FITTINGS FOR PIPES; SUPPORTS FOR PIPES, CABLES OR PROTECTIVE TUBING; MEANS FOR THERMAL INSULATION IN GENERAL
    • F16L41/00—Branching pipes; Joining pipes to walls
    • F16L41/08—Joining pipes to walls or pipes, the joined pipe axis being perpendicular to the plane of the wall or to the axis of another pipe
    • 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
    • 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)
  • Plasma & Fusion (AREA)
  • High Energy & Nuclear Physics (AREA)
  • Mechanical Engineering (AREA)
  • Pressure Welding/Diffusion-Bonding (AREA)

Abstract

A joint assembly between (a) the free edge of a metallic sealing sheet anchored in the interior wall of a concrete vessel, partic. for a press. water nuclear reactor, provided with an orifice delimiting that free edge and (b) a pipe mounted in the orifice and opening into the interior of the vessel, a narrow slot of width 3 mm communicating with the interior of the vessel is delimited (c) by a sleeve free to expand, the edges of which are connected respectively to the pipe supported thereon and to a sheath partly covering the inner wall of the orifice from the outside of the vessel and (d) by a tube prolonging the sheath into the interior of the vessel and connected in sealed manner to the free edge of the metallic sealing sheet. Provides a simple yet reliable joint permitting free expansion of the pipe without the risk of damaging stresses arising in the metal sheet due to thermal gradients.
FR7505350A 1975-02-20 1975-02-20 Expansion joint for nuclear reactor - connecting a sheet metal liner of a heated pressure vessel to pipe passing into the vessel Granted FR2301764A1 (en)

Priority Applications (1)

Application Number Priority Date Filing Date Title
FR7505350A FR2301764A1 (en) 1975-02-20 1975-02-20 Expansion joint for nuclear reactor - connecting a sheet metal liner of a heated pressure vessel to pipe passing into the vessel

Applications Claiming Priority (1)

Application Number Priority Date Filing Date Title
FR7505350A FR2301764A1 (en) 1975-02-20 1975-02-20 Expansion joint for nuclear reactor - connecting a sheet metal liner of a heated pressure vessel to pipe passing into the vessel

Publications (2)

Publication Number Publication Date
FR2301764A1 true FR2301764A1 (en) 1976-09-17
FR2301764B1 FR2301764B1 (en) 1977-09-30

Family

ID=9151497

Family Applications (1)

Application Number Title Priority Date Filing Date
FR7505350A Granted FR2301764A1 (en) 1975-02-20 1975-02-20 Expansion joint for nuclear reactor - connecting a sheet metal liner of a heated pressure vessel to pipe passing into the vessel

Country Status (1)

Country Link
FR (1) FR2301764A1 (en)

Cited By (3)

* Cited by examiner, † Cited by third party
Publication number Priority date Publication date Assignee Title
EP0023446B1 (en) * 1979-07-25 1984-09-12 Framatome Fixed-point pipe anchoring device
CN108053898A (en) * 2017-12-28 2018-05-18 中广核研究院有限公司 The peace of reactor pressure vessel and reactor pressure vessel note pipe
WO2018109722A1 (en) * 2016-12-16 2018-06-21 Flsmidth A/S Suction pipe inlet device for centrifugal pump

Citations (1)

* Cited by examiner, † Cited by third party
Publication number Priority date Publication date Assignee Title
FR1527302A (en) * 1966-06-15 1968-05-31 Siemens Ag Device for cooling the assembly locations of different materials between pressure tubes and the bottoms of liquid moderator nuclear reactor vessels

Patent Citations (1)

* Cited by examiner, † Cited by third party
Publication number Priority date Publication date Assignee Title
FR1527302A (en) * 1966-06-15 1968-05-31 Siemens Ag Device for cooling the assembly locations of different materials between pressure tubes and the bottoms of liquid moderator nuclear reactor vessels

Cited By (5)

* Cited by examiner, † Cited by third party
Publication number Priority date Publication date Assignee Title
EP0023446B1 (en) * 1979-07-25 1984-09-12 Framatome Fixed-point pipe anchoring device
WO2018109722A1 (en) * 2016-12-16 2018-06-21 Flsmidth A/S Suction pipe inlet device for centrifugal pump
US20190360495A1 (en) * 2016-12-16 2019-11-28 Flsmidth A/S Suction Pipe Inlet Device For Centrifugal Pump
US10907639B2 (en) 2016-12-16 2021-02-02 Flsmidth A/S Suction pipe inlet device for centrifugal pump
CN108053898A (en) * 2017-12-28 2018-05-18 中广核研究院有限公司 The peace of reactor pressure vessel and reactor pressure vessel note pipe

Also Published As

Publication number Publication date
FR2301764B1 (en) 1977-09-30

Similar Documents

Publication Publication Date Title
GB2019942A (en) Installation for generating gas under pressure
GB1426581A (en) Pressure vessel
GB1251917A (en)
FR2301764A1 (en) Expansion joint for nuclear reactor - connecting a sheet metal liner of a heated pressure vessel to pipe passing into the vessel
ZA82754B (en) Apparatus for the pressure-tight fastening of a pipe in a pipe-plate with the aid of a pressure fluid
GB1458559A (en) Temperature measuring device
FR2312092B1 (en)
NO174564C (en) Method of branching pipes
JPS5367152A (en) Heat-pipe heat exchanger and production thereof
GB1519305A (en) Gas-cooled nuclear reactor system
JPS53134101A (en) Steam generating device utilizing integral separator and obliquely extending fluid tube for enclosing wall of furnace
JPS5413455A (en) Uniformly expanding device for tube
GB1015653A (en) Improvements in or relating to tube joints
ES8103440A1 (en) Removable and tight closure device for an opening of a nuclear reactor vessel.
JPS5533932A (en) Mechanical seal
JPS5719967A (en) Safety valve for battery
JPS53132072A (en) Method of covering the inner surface of metal pipe with plastic film
JPS52143312A (en) Steam seal ring
FR2394054A1 (en) Double U=bent heat exchanger tube nest - has high pressure fluid connection between tubes for scale removal
JPS5526404A (en) Detection method of heat pipe getting into performance degradation
FR2300287A1 (en) Pipe connection for metal plate covering concrete casing - useful in nuclear reactors (SW060976)
JPS5371567A (en) Reaction equipment
JPS54102486A (en) Diaphragm floor seal bellows of reactor container
JPS5473351A (en) Construction of transportation pipe for high temperature and high pressure gas
JPS54116732A (en) Conducting passage sealing device

Legal Events

Date Code Title Description
ST Notification of lapse