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GB1271644A - Improvements in nuclear fuel elements - Google Patents

Improvements in nuclear fuel elements

Info

Publication number
GB1271644A
GB1271644A GB35399/68A GB3539968A GB1271644A GB 1271644 A GB1271644 A GB 1271644A GB 35399/68 A GB35399/68 A GB 35399/68A GB 3539968 A GB3539968 A GB 3539968A GB 1271644 A GB1271644 A GB 1271644A
Authority
GB
United Kingdom
Prior art keywords
sheath
fuel
shape
equilateral
july
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
GB35399/68A
Inventor
Shepherd Rigg
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.)
UK Atomic Energy Authority
Original Assignee
UK Atomic Energy Authority
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 UK Atomic Energy Authority filed Critical UK Atomic Energy Authority
Priority to GB35399/68A priority Critical patent/GB1271644A/en
Publication of GB1271644A publication Critical patent/GB1271644A/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
    • G21C3/04Constructional details
    • G21C3/06Casings; Jackets
    • 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

1,271,644. Fuel elements. UNITED KING- DOM ATOMIC ENERGY AUTHORITY. 30 July, 1969 [24 July, 1968], No. 35399/68. Heading G6C. A nuclear fuel sheath has, in cross-section, an internal periphery generally in the shape of a closed three-sided figure having equilateral curved sides such that at least preliminary growth of the fuel housed within the sheath is accommodated by change of shape of the sheath without significant increase of its circumferential dimensions. The sheath may be metal or ceramic. In the embodiment shown in Fig. 2, where circular UO 2 fuel pellets 20 having a bore 22 are housed in a stainless steel sheath 21 in the form of an equilateral curved triangle, there will be unequal temperature distribution as between places 24 where the fuel is in contact with the sheath and places 25 where there is a gap between fuel and sheath. The effect of this inequality can be reduced by having the pellets segmented as indicated by the broken lines 26, or by having the bore 22 modified in shape as indicated by the broken lines 27, or both. The temperature variation around the sheath should preferably be less than 5%, and this could be controlled by modifying the sheath thickness and by means of finning around the sheath. In an alternative embodiment, the fuel is in the form of a non-circular UO 2 rod which has the same shape in cross-section as the area bounded by the internal periphery of the sheath (Fig. 1, not shown).
GB35399/68A 1968-07-24 1968-07-24 Improvements in nuclear fuel elements Expired GB1271644A (en)

Priority Applications (1)

Application Number Priority Date Filing Date Title
GB35399/68A GB1271644A (en) 1968-07-24 1968-07-24 Improvements in nuclear fuel elements

Applications Claiming Priority (1)

Application Number Priority Date Filing Date Title
GB35399/68A GB1271644A (en) 1968-07-24 1968-07-24 Improvements in nuclear fuel elements

Publications (1)

Publication Number Publication Date
GB1271644A true GB1271644A (en) 1972-04-19

Family

ID=10377296

Family Applications (1)

Application Number Title Priority Date Filing Date
GB35399/68A Expired GB1271644A (en) 1968-07-24 1968-07-24 Improvements in nuclear fuel elements

Country Status (1)

Country Link
GB (1) GB1271644A (en)

Cited By (2)

* Cited by examiner, † Cited by third party
Publication number Priority date Publication date Assignee Title
US9406410B2 (en) 2009-12-04 2016-08-02 Commissariat A L'energie Atomique Et Aux Energies Alternatives Nuclear fuel rod and method of manufacturing pellets for such a rod
FR3149720A1 (en) * 2023-06-07 2024-12-13 Commissariat A L'energie Atomique Et Aux Energies Alternatives Nuclear reactor pencil

Cited By (2)

* Cited by examiner, † Cited by third party
Publication number Priority date Publication date Assignee Title
US9406410B2 (en) 2009-12-04 2016-08-02 Commissariat A L'energie Atomique Et Aux Energies Alternatives Nuclear fuel rod and method of manufacturing pellets for such a rod
FR3149720A1 (en) * 2023-06-07 2024-12-13 Commissariat A L'energie Atomique Et Aux Energies Alternatives Nuclear reactor pencil

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