GB1292335A - Improvements in and relating to fuel elements for nuclear reactors - Google Patents

Improvements in and relating to fuel elements for nuclear reactors

Info

Publication number
GB1292335A
GB1292335A GB20753/69A GB2075369A GB1292335A GB 1292335 A GB1292335 A GB 1292335A GB 20753/69 A GB20753/69 A GB 20753/69A GB 2075369 A GB2075369 A GB 2075369A GB 1292335 A GB1292335 A GB 1292335A
Authority
GB
United Kingdom
Prior art keywords
fuel
fins
container
fuel member
graphite
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
GB20753/69A
Inventor
James Andrew Robinson
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.)
Nuclear Power Group Ltd
Original Assignee
Nuclear Power Group Ltd
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 Nuclear Power Group Ltd filed Critical Nuclear Power Group Ltd
Priority to GB20753/69A priority Critical patent/GB1292335A/en
Priority to DE19702019302 priority patent/DE2019302A1/en
Priority to BE749342D priority patent/BE749342A/en
Publication of GB1292335A publication Critical patent/GB1292335A/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
    • G21C3/28Fuel elements with fissile or breeder material in solid 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

1292335 Fuel elements NUCLEAR POWER GROUP Ltd 31 March 1970 [23 April 1969] 20753/69 Heading G6C A fuel element comprises a nuclear fuel member located in a graphite container, adjacent surfaces of both the container and the fuel member having fins, the fins on the container overlapping radially those on the fuel member. Initially the fuel member is a close fit inside the container so as to minimize gaps at the fuelgraphite interface. Differential shrinkage of fuel member and graphite during operation causes gaps to open up which can result in overheating of the fuel member. The radial height of the fins is such, however, that an overlap is maintained even after the gaps have opened up to the maximum degree. Various fin shapes are possible and in one embodiment the fins are of sawtooth form so designed as to induce relative rotation between the fuel member and the container. As a result of the overlapping fins heat can be transferred in a circumferential direction which means that the temperature drop across the fuel-graphite interface is less dependent on radial gap width than with elements without fins of the kind described. Any contact between the fins reduces the temperature difference between the fuel and graphite and hence reduces the risk of overheating of the fuel in local regions. Typically the fuel member is of enriched uranium in particulate form in a graphite matrix. The fuel member may be annular in crosssection and have both inner and outer graphite containers, each provided with fins overlapping radially corresponding fins on the fuel member. In this case, the coolant flows between the outer surface of the inner container and the inner surface of the fuel member, as well as over the outer surface of the outer container and the inner surface of the inner container.
GB20753/69A 1969-04-23 1969-04-23 Improvements in and relating to fuel elements for nuclear reactors Expired GB1292335A (en)

Priority Applications (3)

Application Number Priority Date Filing Date Title
GB20753/69A GB1292335A (en) 1969-04-23 1969-04-23 Improvements in and relating to fuel elements for nuclear reactors
DE19702019302 DE2019302A1 (en) 1969-04-23 1970-04-22 Nuclear reactor fuel element
BE749342D BE749342A (en) 1969-04-23 1970-04-22 IMPROVEMENTS IN FUEL ELEMENTS FOR NUCLEAR REACTORS

Applications Claiming Priority (1)

Application Number Priority Date Filing Date Title
GB20753/69A GB1292335A (en) 1969-04-23 1969-04-23 Improvements in and relating to fuel elements for nuclear reactors

Publications (1)

Publication Number Publication Date
GB1292335A true GB1292335A (en) 1972-10-11

Family

ID=10151076

Family Applications (1)

Application Number Title Priority Date Filing Date
GB20753/69A Expired GB1292335A (en) 1969-04-23 1969-04-23 Improvements in and relating to fuel elements for nuclear reactors

Country Status (3)

Country Link
BE (1) BE749342A (en)
DE (1) DE2019302A1 (en)
GB (1) GB1292335A (en)

Families Citing this family (1)

* Cited by examiner, † Cited by third party
Publication number Priority date Publication date Assignee Title
CA1195441A (en) * 1982-03-03 1985-10-15 Stefan Begej Nuclear reactor fuel element having improved heat transfer

Also Published As

Publication number Publication date
DE2019302A1 (en) 1971-02-25
BE749342A (en) 1970-10-01

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Legal Events

Date Code Title Description
PS Patent sealed
PLNP Patent lapsed through nonpayment of renewal fees