GB1421987A - Fuel element for high temperature reactors - Google Patents

Fuel element for high temperature reactors

Info

Publication number
GB1421987A
GB1421987A GB775173A GB775173A GB1421987A GB 1421987 A GB1421987 A GB 1421987A GB 775173 A GB775173 A GB 775173A GB 775173 A GB775173 A GB 775173A GB 1421987 A GB1421987 A GB 1421987A
Authority
GB
United Kingdom
Prior art keywords
matrix
fuel
block
graphite
inserts
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
GB775173A
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.)
Nukem GmbH
Original Assignee
Nukem GmbH
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
Priority claimed from DE19722208855 external-priority patent/DE2208855C3/en
Application filed by Nukem GmbH filed Critical Nukem GmbH
Publication of GB1421987A publication Critical patent/GB1421987A/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
    • G21C3/28Fuel 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)
  • Ceramic Products (AREA)

Abstract

1421987 Fuel elements NUKEM GmbH 16 Feb 1973 [25 Feb 1972] 7751/73 Heading G6C A fuel element for a high temperature reactor comprises a graphite block formed with bores within which fuel inserts fit without intervening gaps. The fuel inserts each consist of coated fuel particles within a graphite matrix. They are produced by pressing from the coated fuel particles and a matrix powder mix and, in one method, the green pressings thus obtained are introduced into the bores in the graphite block. During the subsequent coking and heat-treatment operations, these inserts expand and fit tightly without gaps into the bores. The composition of the pressing powder is such that the resultant matrix has as high a thermal conductivity as the graphite block and that no gap is formed between the insert and the block during reactor operation. This is achieved by virtue of the fact that, from the beginning of fuel exposure onwards, the matrix expands more than the block, contracts less than the block or expands while the block contracts, with the result that at no time during operation of the reactor is a gap formed. The matrix consists of natural graphite alone or with at most 15%, preferably less than 10%, by weight of binder. With such a binder content, expansion of the matrix occurs on coking. In a further embodiment, the graphite matrix also contains up to 25% by weight electrographite and up to 25% by weight binder (the remainder of the matrix being natural graphite). The binder used for the matrix preferably consists of a readily graphitized material such as coal-tar pitch. In an alternative method, the fuel inserts are coked and calcined on their own and only thereafter introduced into the block. The matrix in this case consists of natural graphite with less than 5% by weight of binder. The fuel inserts can be additionally provided with a thin fuel-free shell. Because the matrix is selected to undergo greater thermal expansion than the structural graphite, the fuel inserts fit tightly in the bores without any gaps when the fuel element is heated to its working temperature in the reactor. Any stresses in the matrix are quickly dissipated by creeping so that they never become critical.
GB775173A 1972-02-25 1973-02-16 Fuel element for high temperature reactors Expired GB1421987A (en)

Applications Claiming Priority (1)

Application Number Priority Date Filing Date Title
DE19722208855 DE2208855C3 (en) 1972-02-25 Process for the production of prismatic block fuel elements for high-temperature reactors

Publications (1)

Publication Number Publication Date
GB1421987A true GB1421987A (en) 1976-01-21

Family

ID=5837014

Family Applications (1)

Application Number Title Priority Date Filing Date
GB775173A Expired GB1421987A (en) 1972-02-25 1973-02-16 Fuel element for high temperature reactors

Country Status (3)

Country Link
FR (1) FR2172946B1 (en)
GB (1) GB1421987A (en)
IT (1) IT958994B (en)

Also Published As

Publication number Publication date
FR2172946B1 (en) 1977-04-01
DE2208855A1 (en) 1973-09-06
FR2172946A1 (en) 1973-10-05
DE2208855B2 (en) 1976-02-19
IT958994B (en) 1973-10-30

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Legal Events

Date Code Title Description
PS Patent sealed
PCNP Patent ceased through non-payment of renewal fee