GB1139990A - Nuclear fuel element - Google Patents

Nuclear fuel element

Info

Publication number
GB1139990A
GB1139990A GB58735/67A GB5873567A GB1139990A GB 1139990 A GB1139990 A GB 1139990A GB 58735/67 A GB58735/67 A GB 58735/67A GB 5873567 A GB5873567 A GB 5873567A GB 1139990 A GB1139990 A GB 1139990A
Authority
GB
United Kingdom
Prior art keywords
fuel
core
graphite
oxide
funnel
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
GB58735/67A
Inventor
Jacques Stohr
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 GB1139990A publication Critical patent/GB1139990A/en
Expired legal-status Critical Current

Links

Classifications

    • 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
    • G21C3/16Details of the construction within the casing
    • 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
    • G21C3/26Fuel elements with fissile or breeder material in powder form within a non-active casing
    • 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)

Abstract

1,139,990. Fuel elements. COMMISSARIAT A L'ENERGIE ATOMIQUE. 27 Dec., 1967 [25 Jan., 1967], No. 58735/67. Heading G6C. A fuel element comprises a mass of ceramic fuel 14, e.g. an oxide (UO 2 , PuO 2 or a mixed oxide of U and Pu), carbide or nitride, in finely divided form, compacted in a tubular zone between a metallic can 6 and a core 12 of a porous, non-fissile refractory material retaining a substantial resistance to compression and creep at the working temperature of the fuel element and having end parts that project out from the fuel material and are covered by the end plugs 10 of the can. The core 12, which may be of graphite, Al 2 O 3 , MgO, ZrO 2 or SiO 2 , serves to absorb fission product gases and to secure the mechanical rigidity of the element. A graphite core has the disadvantage of reacting with the oxide fuel materials but the reaction kinetics, which are slow if the contact temperature between the fuel and the graphite is low and if the external pressure of the coolant gas is high, result in acceptable valves in the case of a reactor operating with a coolant gas at a high pressure, e.g. 60 bars. In order to avoid any reaction, however, the graphite core may be coated with a refractory oxide, e.g. Al 2 O 3 , MgO or ZrO 2 , by spraying it with a suspension of the refractory oxide in a flow of hot gas. In a process of manufacturing such a fuel element, a graphite core is prepared by machining or extruding a carbon mixture which is subjected to a graphitizing treatment and also to a treatment for increasing its porosity. The can 6 previously equipped with the lower plug 10 is placed vertically on a frame 18 and fitted with a loading funnel 20 provided with a central hub 22 through which the core 12 is slipped into position in the can 6. The fuel material is then poured into the funnel 20 and compacted in the can 6 by vibration of the frame 18. These operations are performed within a gas-tight vessel 24 in which a vacuum is maintained. When the filling is completed, the funnel 20 is removed and the end plug placed in position and screwed to the can 6, e.g. by electron beam welding.
GB58735/67A 1967-01-25 1967-12-27 Nuclear fuel element Expired GB1139990A (en)

Applications Claiming Priority (1)

Application Number Priority Date Filing Date Title
FR92492A FR1525099A (en) 1967-01-25 1967-01-25 Nuclear fuel element

Publications (1)

Publication Number Publication Date
GB1139990A true GB1139990A (en) 1969-01-15

Family

ID=8624360

Family Applications (1)

Application Number Title Priority Date Filing Date
GB58735/67A Expired GB1139990A (en) 1967-01-25 1967-12-27 Nuclear fuel element

Country Status (2)

Country Link
FR (1) FR1525099A (en)
GB (1) GB1139990A (en)

Cited By (2)

* Cited by examiner, † Cited by third party
Publication number Priority date Publication date Assignee Title
DE3920673A1 (en) * 1988-06-27 1990-01-04 Babcock & Wilcox Co SPRING-PACKED PARTICLE BED FUEL ELEMENT
DE3919286A1 (en) * 1988-09-23 1990-03-29 Babcock & Wilcox Co Nuclear fuel element for particle bed reactor - with fuel bed in annular space between porous external frit contg. fissile material, and internal fit

Families Citing this family (2)

* Cited by examiner, † Cited by third party
Publication number Priority date Publication date Assignee Title
BE754790A (en) * 1969-08-22 1971-01-18 Euratom PROCESS FOR PREPARING FUEL ELEMENTS
EP0132911B1 (en) * 1983-05-06 1988-06-29 The Babcock & Wilcox Company Annular fuel rods for nuclear reactors

Cited By (2)

* Cited by examiner, † Cited by third party
Publication number Priority date Publication date Assignee Title
DE3920673A1 (en) * 1988-06-27 1990-01-04 Babcock & Wilcox Co SPRING-PACKED PARTICLE BED FUEL ELEMENT
DE3919286A1 (en) * 1988-09-23 1990-03-29 Babcock & Wilcox Co Nuclear fuel element for particle bed reactor - with fuel bed in annular space between porous external frit contg. fissile material, and internal fit

Also Published As

Publication number Publication date
FR1525099A (en) 1968-05-17

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