GB941668A - Nuclear reactor duct structure - Google Patents

Nuclear reactor duct structure

Info

Publication number
GB941668A
GB941668A GB14038/60A GB1403860A GB941668A GB 941668 A GB941668 A GB 941668A GB 14038/60 A GB14038/60 A GB 14038/60A GB 1403860 A GB1403860 A GB 1403860A GB 941668 A GB941668 A GB 941668A
Authority
GB
United Kingdom
Prior art keywords
silica
tube
tubes
fuel
guide
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
GB14038/60A
Inventor
Lucien Alfille
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 GB941668A publication Critical patent/GB941668A/en
Expired legal-status Critical Current

Links

Classifications

    • GPHYSICS
    • G21NUCLEAR PHYSICS; NUCLEAR ENGINEERING
    • G21CNUCLEAR REACTORS
    • G21C1/00Reactor types
    • G21C1/04Thermal reactors ; Epithermal reactors
    • G21C1/06Heterogeneous reactors, i.e. in which fuel and moderator are separated
    • G21C1/14Heterogeneous reactors, i.e. in which fuel and moderator are separated moderator being substantially not pressurised, e.g. swimming-pool reactor
    • G21C1/16Heterogeneous 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
    • G21C1/18Heterogeneous 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
    • G21C1/20Heterogeneous 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
    • GPHYSICS
    • G21NUCLEAR PHYSICS; NUCLEAR ENGINEERING
    • G21CNUCLEAR REACTORS
    • G21C15/00Cooling arrangements within the pressure vessel containing the core; Selection of specific coolants
    • G21C15/02Arrangements or disposition of passages in which heat is transferred to the coolant; Coolant flow control devices
    • GPHYSICS
    • G21NUCLEAR PHYSICS; NUCLEAR ENGINEERING
    • G21CNUCLEAR REACTORS
    • G21C15/00Cooling arrangements within the pressure vessel containing the core; Selection of specific coolants
    • G21C15/20Partitions or thermal insulation between fuel channel and moderator
    • GPHYSICS
    • G21NUCLEAR PHYSICS; NUCLEAR ENGINEERING
    • G21CNUCLEAR REACTORS
    • G21C3/00Reactor fuel elements and their assemblies; Selection of substances for use as reactor fuel elements
    • G21C3/02Fuel elements
    • G21C3/04Constructional details
    • G21C3/06Casings; Jackets
    • G21C3/12Means forming part of the element for locating it within the reactor core
    • GPHYSICS
    • G21NUCLEAR PHYSICS; NUCLEAR ENGINEERING
    • G21CNUCLEAR REACTORS
    • G21C3/00Reactor fuel elements and their assemblies; Selection of substances for use as reactor fuel elements
    • G21C3/30Assemblies of a number of fuel elements in the form of a rigid unit
    • G21C3/32Bundles of parallel pin-, rod-, or tube-shaped fuel elements
    • YGENERAL 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
    • Y02TECHNOLOGIES OR APPLICATIONS FOR MITIGATION OR ADAPTATION AGAINST CLIMATE CHANGE
    • Y02EREDUCTION OF GREENHOUSE GAS [GHG] EMISSIONS, RELATED TO ENERGY GENERATION, TRANSMISSION OR DISTRIBUTION
    • Y02E30/00Energy generation of nuclear origin
    • Y02E30/30Nuclear fission reactors

Landscapes

  • Physics & Mathematics (AREA)
  • Engineering & Computer Science (AREA)
  • Plasma & Fusion (AREA)
  • General Engineering & Computer Science (AREA)
  • High Energy & Nuclear Physics (AREA)
  • Monitoring And Testing Of Nuclear Reactors (AREA)
  • Organic Low-Molecular-Weight Compounds And Preparation Thereof (AREA)
  • Devices And Processes Conducted In The Presence Of Fluids And Solid Particles (AREA)

Abstract

941,668. Nuclear reactors. COMMISSARIAT A L'ENERGIE ATOMIQUE. April 21,1960 [April 29, 1959], No. 14038/60. Heading G6C. Vitreous silica is used as a guide tube for fuel elements in a nuclear reactor; the silica has a very smooth surface, and flexible and deformable connecting members are put at the ends of the tube, around it, and between different sections of it. Fig. 3 shows a channel of a CO 2 -cooled D 2 O- moderated reactor, comprising a pressure tube 3, thermal insulation 4, and vitreous silica 5. A spring and guide bush 14 are provided at one end to absorb changes in length of the silica; the sections of the silica tube are separated by plastic metal rings 15 of sintered A1 welded to metal foil 16, Fig. 5. Fig. 7 shows an air-cooled, sintered beryllia-moderated reactor having silica guide and pressure tubes 5 supported by plastic metal bush 20 of low carbon stainless steel on steel plate 19 and by a refractory alloy ring 21a and a plastic metal bush in steel plate 23. Fuel is supended from a support 24; fuel and pressure tube are centred by refractory alloy springs. The silica tube may be smooth or finned, opaque or transparent, moulded or drawn; it may be polished mechanically or with hydrogen fluoride. The Specification also describes existing reactors: one has CO 2 coolant, D 2 O moderator, and Mg alloy pressure tubes containing and insulated from fuel element guide tubes, the Mg alloy tubes being enclosed in receiving tubes mounted in the reactor; another has a combined pressure and receiving tube of Be. A beryllia-moderated reactor using sintered U-Mgo fuel, and guide tubes of Al, Mg, Zr and their alloys, Be and stainless steel, are mentioned.
GB14038/60A 1959-04-29 1960-04-21 Nuclear reactor duct structure Expired GB941668A (en)

Applications Claiming Priority (1)

Application Number Priority Date Filing Date Title
FR793521A FR1233087A (en) 1959-04-29 1959-04-29 New use of vitreous silica

Publications (1)

Publication Number Publication Date
GB941668A true GB941668A (en) 1963-11-13

Family

ID=8714292

Family Applications (1)

Application Number Title Priority Date Filing Date
GB14038/60A Expired GB941668A (en) 1959-04-29 1960-04-21 Nuclear reactor duct structure

Country Status (7)

Country Link
BE (1) BE589760A (en)
CH (1) CH370169A (en)
DE (1) DE1238113B (en)
FR (1) FR1233087A (en)
GB (1) GB941668A (en)
LU (1) LU38532A1 (en)
NL (1) NL250968A (en)

Families Citing this family (2)

* Cited by examiner, † Cited by third party
Publication number Priority date Publication date Assignee Title
NL277876A (en) * 1961-05-02 1900-01-01
FR1387264A (en) * 1963-12-18 1965-01-29 Commissariat Energie Atomique nuclear reactor fuel element

Family Cites Families (3)

* Cited by examiner, † Cited by third party
Publication number Priority date Publication date Assignee Title
NL103807C (en) * 1955-07-27
DE1010660B (en) * 1956-04-19 1957-06-19 Siemens Ag Protective sleeve for fissile material elements of nuclear reactors
DE1031901B (en) * 1957-01-26 1958-06-12 Siemens Ag Gas-cooled nuclear reactor

Also Published As

Publication number Publication date
BE589760A (en) 1960-08-01
NL250968A (en)
CH370169A (en) 1963-06-30
DE1238113B (en) 1967-04-06
FR1233087A (en) 1960-10-12
LU38532A1 (en)

Similar Documents

Publication Publication Date Title
GB807817A (en) Fuel-breeder fuel element for nuclear reactor
GB1537225A (en) Fast neutron nuclear reactor
GB1408375A (en) Method of fabricating nuclear reactor elements
GB896343A (en) Nuclear reactor fuel element
GB845804A (en) Improvements in or relating to elements of fissionable material
GB911466A (en) Improvements in methods of sheathing hollow fuel elements for nuclear reactors
GB915491A (en) Modular core units for a nuclear reactor
GB941668A (en) Nuclear reactor duct structure
GB887881A (en) Improvements in heat transfer systems for nuclear reactors
GB901667A (en) Concentric tubular nuclear fuel elements
GB833647A (en) Improvements in or relating to nuclear reactors
GB877418A (en) Improvements in fuel arrangements for use in nuclear reactors having vertical channels
GB921710A (en) Improvements in or relating to nuclear reactors
GB847220A (en) Improvements in or relating to heat exchange elements suitable for use as fuel elements for nuclear reactors
GB881790A (en) Improvements in or relating to nuclear reactors
GB906827A (en) Improvements in nuclear reactors
GB907344A (en) Improvements in methods and devices for securing fuel elements in nuclear reactor tubular channels
US3284315A (en) Nuclear reactor fuel element assembly
GB907625A (en) Improvements in nuclear fuel elements
GB903489A (en) Improvements in or relating to core elements for nuclear reactors
GB1361700A (en) Nuclear fuel assembly
GB1320476A (en) Liquid cooled nuclear reactor including a neutron flux measurement installation
GB974129A (en) Improvements relating to nuclear reactors
GB835132A (en) Improvements in or relating to fuel elements for nuclear reactors
GB917461A (en) Fuel element for a nuclear reactor