GB946256A - Improvements in tubes for nuclear reactors - Google Patents

Improvements in tubes for nuclear reactors

Info

Publication number
GB946256A
GB946256A GB7505/61A GB750561A GB946256A GB 946256 A GB946256 A GB 946256A GB 7505/61 A GB7505/61 A GB 7505/61A GB 750561 A GB750561 A GB 750561A GB 946256 A GB946256 A GB 946256A
Authority
GB
United Kingdom
Prior art keywords
sleeve
tube
shell
core
reactor
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
GB7505/61A
Inventor
Henri Foulquier
Claude Bridoux
Jacques Stohr
Paul Thome
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
Publication of GB946256A publication Critical patent/GB946256A/en
Expired legal-status Critical Current

Links

Classifications

    • 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
    • F16L5/00—Devices for use where pipes, cables or protective tubing pass through walls or partitions
    • F16L5/02—Sealing
    • F16L5/022—Sealing by welding
    • G—PHYSICS
    • G21—NUCLEAR PHYSICS; NUCLEAR ENGINEERING
    • G21C—NUCLEAR REACTORS
    • G21C1/00—Reactor types
    • G21C1/04—Thermal reactors ; Epithermal reactors
    • G21C1/06—Heterogeneous reactors, i.e. in which fuel and moderator are separated
    • G21C1/14—Heterogeneous reactors, i.e. in which fuel and moderator are separated moderator being substantially not pressurised, e.g. swimming-pool reactor
    • G21C1/16—Heterogeneous reactors, i.e. in which fuel and moderator are separated moderator being substantially not pressurised, e.g. swimming-pool reactor moderator and coolant being different or separated, e.g. sodium-graphite reactor, sodium-heavy water reactor or organic coolant-heavy water reactor
    • G21C1/18—Heterogeneous reactors, i.e. in which fuel and moderator are separated moderator being substantially not pressurised, e.g. swimming-pool reactor moderator and coolant being different or separated, e.g. sodium-graphite reactor, sodium-heavy water reactor or organic coolant-heavy water reactor coolant being pressurised
    • G21C1/20—Heterogeneous reactors, i.e. in which fuel and moderator are separated moderator being substantially not pressurised, e.g. swimming-pool reactor moderator and coolant being different or separated, e.g. sodium-graphite reactor, sodium-heavy water reactor or organic coolant-heavy water reactor coolant being pressurised moderator being liquid, e.g. pressure-tube reactor
    • 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
    • G21C15/22—Structural association of coolant tubes with headers
    • 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)
  • General Engineering & Computer Science (AREA)
  • Physics & Mathematics (AREA)
  • Plasma & Fusion (AREA)
  • High Energy & Nuclear Physics (AREA)
  • Mechanical Engineering (AREA)
  • Physical Or Chemical Processes And Apparatus (AREA)
  • Arc Welding In General (AREA)

Abstract

946,256. Pipe couplings. COMMISSARIAT A L'ENERGIE ATOMIQUE. March 1, 1961 [March 1, 1960], No. 7505/61. Heading F2G. [Also in Division G6] A tube for passing in fluid-tight manner through the core of a nuclear reactor, e.g. a tube for conveying gas coolant through a heavy water moderated reactor, comprises a central portion 1 of zirconium or a zirconium alloy of low neutron absorption which, being difficult to weld or fuse to the corresponding adjoining parts of the core shell 5, is jointed, before mounting in the core in fluid-tight manner at least at one end to a sleeve 2 of a material such as stainless steel capable of being welded or fused to the shell 5. The jointing of the central portion 1 to the sleeve 2 may be effected by means of screw threads (as shown); drawing the two elements, engaged one within the other, through a narrow annular opening; or by fitting a mandrel within the two elements engaged one within the other, the mandrel having a coefficient of thermal expansion greater than that of the inside element, and heating in a vacuum or an inert atmosphere. The sleeve 2 is end-welded at 12 to a surrounding collar 9, itself endwelded at 11 to a coolant duet 8 which pene trates the concrete shield 7, the light watershield 6, the wall 10 separating these two, and the shell 5. The diameter of the duct 8 is such as to allow the passage of the tube on its insertion into or removal from the reactor.
GB7505/61A 1960-03-01 1961-03-01 Improvements in tubes for nuclear reactors Expired GB946256A (en)

Applications Claiming Priority (1)

Application Number Priority Date Filing Date Title
FR820015A FR1263814A (en) 1960-03-01 1960-03-01 Pressure tube for nuclear reactor

Publications (1)

Publication Number Publication Date
GB946256A true GB946256A (en) 1964-01-08

Family

ID=8726110

Family Applications (1)

Application Number Title Priority Date Filing Date
GB7505/61A Expired GB946256A (en) 1960-03-01 1961-03-01 Improvements in tubes for nuclear reactors

Country Status (8)

Country Link
BE (1) BE600589A (en)
CH (1) CH375802A (en)
DE (1) DE1208422B (en)
FR (1) FR1263814A (en)
GB (1) GB946256A (en)
LU (1) LU39825A1 (en)
NL (1) NL261834A (en)
NO (1) NO115015B (en)

Cited By (1)

* Cited by examiner, † Cited by third party
Publication number Priority date Publication date Assignee Title
US8678445B2 (en) 2008-02-08 2014-03-25 J. Eberspaecher Gmbh & Co. Kg Component connection

Families Citing this family (2)

* Cited by examiner, † Cited by third party
Publication number Priority date Publication date Assignee Title
US3440140A (en) * 1965-12-03 1969-04-22 Ca Atomic Energy Ltd Protection of zirconium alloy components against hydriding
EP0465702A1 (en) * 1990-07-11 1992-01-15 Westinghouse Electric Corporation Apparatus and method for repairing welded flow connections provided through high pressure casings of nuclear power plant pumps or like devices

Family Cites Families (8)

* Cited by examiner, † Cited by third party
Publication number Priority date Publication date Assignee Title
US2915446A (en) * 1954-11-29 1959-12-01 Asea Ab Gas cooled nuclear reactor
DE1022061B (en) * 1955-03-19 1958-01-02 Ver Kesselwerke Ag Connection between an austenitic and a ferritic tube
NL102737C (en) * 1956-08-02
FR1162178A (en) * 1956-08-24 1958-09-09 Cie Constr Gros Mat Electromec Method of fixing copper-nickel tubes on steel walls
DE1031901B (en) * 1957-01-26 1958-06-12 Siemens Ag Gas-cooled nuclear reactor
BE565765A (en) * 1957-03-19
FR1204410A (en) * 1957-04-09 1960-01-26 Ind Fernand Courtoy Bureau Et Improvements made to welded joints between ferritic and austenitic steels
BE568855A (en) * 1957-06-24 1900-01-01

Cited By (1)

* Cited by examiner, † Cited by third party
Publication number Priority date Publication date Assignee Title
US8678445B2 (en) 2008-02-08 2014-03-25 J. Eberspaecher Gmbh & Co. Kg Component connection

Also Published As

Publication number Publication date
NL261834A (en) 1900-01-01
LU39825A1 (en) 1961-04-24
BE600589A (en) 1961-06-16
NO115015B (en) 1968-07-01
CH375802A (en) 1964-03-15
FR1263814A (en) 1961-06-19
DE1208422B (en) 1966-01-05

Similar Documents

Publication Publication Date Title
GB1152305A (en) Burnable Poison Rods for a Nuclear Reactor
GB845804A (en) Improvements in or relating to elements of fissionable material
GB834371A (en) High flux homogeneous nuclear process and reactor with circulating fissile material
GB1279084A (en) Improvements in or relating to nuclear reactors
ES449721A1 (en) Nuclear reactor plant
GB946256A (en) Improvements in tubes for nuclear reactors
GB911466A (en) Improvements in methods of sheathing hollow fuel elements for nuclear reactors
GB1128826A (en) Fuel assembly for a nuclear reactor cooled by a liquid metal
ES8100533A1 (en) Device for the detachable mounting of an electric resistance heating element in the pressurizer of a nuclear reactor.
ES486194A1 (en) Connection of two pipes.
DE3277932D1 (en) Heat exchangers and methods of construction thereof
GB847636A (en) Improvements in or relating to nuclear reactor refuelling devices
GB884298A (en) Improvements in nuclear reactors
GB925000A (en)
GB978377A (en) A device for closing the end of a tube or pipe
GB835257A (en) Improvements in and relating to nuclear reactors
GB1083837A (en) Method and apparatus for increasing burnout heat flux in reactor pressure tubes
GB954529A (en) Steam-water mixing device for steam-cooled reactor
GB907344A (en) Improvements in methods and devices for securing fuel elements in nuclear reactor tubular channels
KR830001692B1 (en) Guide tube fixture of reactor fuel assembly
GB1359085A (en) Device for scraping a deposit of metal on a cylindrical bar
JPS56160588A (en) Apparatus for reducing heat stress on bottom of vertical heat exchanger
GB1010644A (en) Nuclear reactor fuelled with settled particulate
GB802998A (en) Improvements in or relating to sheathed annular bodies
JPS526893A (en) Assembly of nuclear fuel