US3492379A - Method of preparing nuclear fuel elements incorporating fission product retaining fuel particles - Google Patents

Method of preparing nuclear fuel elements incorporating fission product retaining fuel particles Download PDF

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Publication number
US3492379A
US3492379A US630408A US3492379DA US3492379A US 3492379 A US3492379 A US 3492379A US 630408 A US630408 A US 630408A US 3492379D A US3492379D A US 3492379DA US 3492379 A US3492379 A US 3492379A
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US
United States
Prior art keywords
particles
resin
fission product
nuclear fuel
product retaining
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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 - Lifetime
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US630408A
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English (en)
Inventor
Geoffrey Brian Redding
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UK Atomic Energy Authority
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UK Atomic Energy Authority
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Publication date
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    • G—PHYSICS
    • G21—NUCLEAR PHYSICS; NUCLEAR ENGINEERING
    • G21C—NUCLEAR REACTORS
    • G21C3/00—Reactor fuel elements and their assemblies; Selection of substances for use as reactor fuel elements
    • G21C3/02—Fuel elements
    • G21C3/04—Constructional details
    • G—PHYSICS
    • G21—NUCLEAR PHYSICS; NUCLEAR ENGINEERING
    • G21C—NUCLEAR REACTORS
    • G21C21/00—Apparatus or processes specially adapted to the manufacture of reactors or parts thereof
    • G21C21/02—Manufacture of fuel elements or breeder elements contained in non-active casings
    • G—PHYSICS
    • G21—NUCLEAR PHYSICS; NUCLEAR ENGINEERING
    • G21C—NUCLEAR REACTORS
    • G21C3/00—Reactor fuel elements and their assemblies; Selection of substances for use as reactor fuel elements
    • G21C3/42—Selection of substances for use as reactor fuel
    • G21C3/58—Solid reactor fuel Pellets made of fissile material
    • G21C3/62—Ceramic fuel
    • G21C3/626—Coated fuel particles
    • G—PHYSICS
    • G21—NUCLEAR PHYSICS; NUCLEAR ENGINEERING
    • G21C—NUCLEAR REACTORS
    • G21C3/00—Reactor fuel elements and their assemblies; Selection of substances for use as reactor fuel elements
    • G21C3/42—Selection of substances for use as reactor fuel
    • G21C3/58—Solid reactor fuel Pellets made of fissile material
    • G21C3/62—Ceramic fuel
    • G21C3/64—Ceramic dispersion fuel, e.g. cermet
    • Y—GENERAL 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
    • Y02—TECHNOLOGIES OR APPLICATIONS FOR MITIGATION OR ADAPTATION AGAINST CLIMATE CHANGE
    • Y02E—REDUCTION OF GREENHOUSE GAS [GHG] EMISSIONS, RELATED TO ENERGY GENERATION, TRANSMISSION OR DISTRIBUTION
    • Y02E30/00—Energy generation of nuclear origin
    • Y02E30/30—Nuclear fission reactors

Definitions

  • This invention relates to the preparation of nuclear fuel elements incorporating fuel particles coated with an outer layer of fission product retaining material.
  • coated fuel particles be incorporated into fuel elements by mixing the particles with powdered graphite and a bonding agent and then hot pressing the mixture in a suitable die to form an artefact. It has also been proposed to overcoat the particles with a layer of resin treated graphite powder and then to press a batch of these overcoated particles to shape. It has further been suggested that preformed graphite bodies be drilled with blind holes into which loose coated particles are poured and retained in the hole by a closure member.
  • the first two can produce a fuelled body having an even dispersion of fuel in graphite which is considered generally desirable but as both require the addition of graphite to the fuel bearing artefact, when the time comes for reprocessing these artefacts, a large bulk of non-nuclear material has to be processed.
  • the third method does not possess this disadvantage, but nevertheless it introduces a safety hazard in that should a container crack, then the loose particles within it may escape and enter the coolant circuit. It is thought, therefore, that such a construction would not easily satisfy the safety requirements for reactor operation.
  • a method of preparing a nuclear fuel element incorporating fission product retaining fuel particles which resides in applying a thin layer of a thermosetting synthetic resin to the outer surface of the particles, arranging the particles so coated in intimate contact with one another in their operative position and heating the particles in situ to cure the resin and fix the particles in position.
  • the fission product retaining particles are coated with a layer of phenoformaldehyde resin e.-g. of a thickness of 10 microns, and then the particles are poured into holes formed in a carrier member after which they are heated so as to adhere to one another and to the walls of the hole on curing.
  • a batch 1 weighing 500 grams of nuclear fuel particles, each about 800 microns diameter and pre-coated with pyrolytic carbon as a fission product retaining layer, was placed in a rotary drum 2 mounted for rotation on an axis, which is in clined at a small angle to the horizontal, by motor 3.
  • the drum 2 has one open end 2a for the introduction of the process materials.
  • the drum was rotated on its axis at a speed of about 30 rpm.
  • a supply 4 of powdered phenoformaldehyde resin in admixture with powdered carbonaceous material such as with graphite powder (20 percent by weight of the resin) and a supply 5 of resin solvent (methylated spirit) were mounted above the drum.
  • the powdered carbonaceous material had the remarkable effect of making the mixed powders flowable without difliculty.
  • Suitable feed pipes 6, 7 were arranged to communicate the supply of mixed resin and graphite powders and solvent with the interior of the drum, the pipes terminating above the open end of the drum at adjacent positions so that the powders and the solvent contacted one another after these materials had left their respective feed pipes and before they entered the drum.
  • the quantity of resin used was about 10 percent by weight of that of the particles i.e. 50 grams of resin. The supply of resin and solvent was then stopped.
  • the particles were then removed from the drum and were found to be free flowing particles and hence easily handlable without sticking together. They could then be poured into any cavity and heated to about C., in situ, to cure the resin and so form a coherent agglomeration of nuclear fuel particles.
  • the particles were incorporated in a fuel element by firstly forming a tube of graphite, about 6 inches long, 1 /2 inch external diameter, /2 inch internal diameter. An annular row of holes each /3 inch diameter spaced on a pitch circle of 1 /5 inch diameter were then drilled axially in the tube wall parallel with the tube axis. Each of the holes was filled in turn with a predetermined quantity of the resin coated particles. A packing density of 50 percent was achieved. The element was then placed in an oven and heated to 180 C. to cure the resin. The element was then allowed to cool and the integral fuel element formed was easily handlable' in any attitude without fear of fuel particles becoming detached. If desired the particles may be vibro compacted before heating.
  • a method of forming a nuclear fuel element incorporating nuclear fuel particles which have been adapted to retain fission products by the application thereto of an outer coating including the step of applying to the outer surface of such particles a further coating comprising a thin layer primarily of thermosetting synthetic resin, disposing these particles in substantially unpressed, free, intimate contact with one another, and then heating the particles in that condition to cure the resin and fix the particles in position.
  • a method of forming a nuclear fuel element as claimed in claim 1 in which after the particles have been given said further coating they are poured into a blind hole in a body of neutron moderating material and heated in situ to cure the resin and fix the particles in position.
  • a method of preparing a nuclear fuel element incorporating nuclear fuel particles bearing a fission product retaining layer comprising tumbling the particles in a mixture of powdered thermosetting resin and powdered carbonaceous material, the resin powder having been softened by contact with resin solvent, until the particles acquire a thin layer of the mixed powders, allowing the solvent to evaporate so as to produce substantially free flowing resin coated particles, pouring the particles into a container, and heating them to form a coherent agglomeration of fuel particles.

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  • Engineering & Computer Science (AREA)
  • Physics & Mathematics (AREA)
  • Plasma & Fusion (AREA)
  • General Engineering & Computer Science (AREA)
  • High Energy & Nuclear Physics (AREA)
  • Chemical & Material Sciences (AREA)
  • Ceramic Engineering (AREA)
  • Manufacturing & Machinery (AREA)
  • Dispersion Chemistry (AREA)
  • Solid Fuels And Fuel-Associated Substances (AREA)
  • Monitoring And Testing Of Nuclear Reactors (AREA)
US630408A 1966-04-28 1967-04-12 Method of preparing nuclear fuel elements incorporating fission product retaining fuel particles Expired - Lifetime US3492379A (en)

Applications Claiming Priority (1)

Application Number Priority Date Filing Date Title
GB18767/66A GB1134117A (en) 1966-04-28 1966-04-28 Improvements in or relating to the preparation of nuclear fuel elements

Publications (1)

Publication Number Publication Date
US3492379A true US3492379A (en) 1970-01-27

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ID=10118062

Family Applications (1)

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US630408A Expired - Lifetime US3492379A (en) 1966-04-28 1967-04-12 Method of preparing nuclear fuel elements incorporating fission product retaining fuel particles

Country Status (7)

Country Link
US (1) US3492379A (oth)
AT (1) AT273316B (oth)
BE (1) BE697093A (oth)
CH (1) CH454292A (oth)
GB (1) GB1134117A (oth)
LU (1) LU53454A1 (oth)
NL (1) NL6706058A (oth)

Cited By (7)

* Cited by examiner, † Cited by third party
Publication number Priority date Publication date Assignee Title
US3668284A (en) * 1968-04-22 1972-06-06 Atomic Energy Authority Uk Manufacture of nuclear fuel elements
FR2134518A1 (oth) * 1971-04-28 1972-12-08 Euratom
US3708559A (en) * 1970-03-27 1973-01-02 Atomic Energy Authority Uk Method of making nuclear fuel-containing bodies
US3900317A (en) * 1973-03-06 1975-08-19 Canadian Patents Dev Fe-sn-cu-pb sintered composite metal article and process
US4035452A (en) * 1975-01-21 1977-07-12 General Atomic Company Method of making nuclear fuel bodies
US4073834A (en) * 1975-03-05 1978-02-14 General Atomic Company Method of making nuclear fuel elements
DE3704167C1 (de) * 1987-02-11 1988-08-18 Hobeg Hochtemperaturreaktor Verfahren zum Umhuellen von Granuliergut

Citations (8)

* Cited by examiner, † Cited by third party
Publication number Priority date Publication date Assignee Title
US3141911A (en) * 1963-03-20 1964-07-21 Joseph J Hauth Process for the fabrication of nuclear fuel elements
US3158547A (en) * 1961-06-30 1964-11-24 Air Reduction Method of encapsulating a graphite body containing metallic and ceramic particles
US3173973A (en) * 1962-12-06 1965-03-16 Brockway Marion Clifford Graphite dispersion
US3212989A (en) * 1961-03-21 1965-10-19 Siemens Planiawerke Ag Nuclear fuel element with carbon jacket
US3274068A (en) * 1964-05-05 1966-09-20 Stanley L Koutz Fuel element
US3284314A (en) * 1963-09-05 1966-11-08 Nukem Gmbh Fuel material for nuclear reactors and process and apparatus for its manufacture
US3293332A (en) * 1962-04-13 1966-12-20 Atomic Energy Authority Uk Process for fabricating a fission product retentive nuclear fuel body
US3344211A (en) * 1964-10-30 1967-09-26 Methods of forming nuclear fuel bodies

Patent Citations (8)

* Cited by examiner, † Cited by third party
Publication number Priority date Publication date Assignee Title
US3212989A (en) * 1961-03-21 1965-10-19 Siemens Planiawerke Ag Nuclear fuel element with carbon jacket
US3158547A (en) * 1961-06-30 1964-11-24 Air Reduction Method of encapsulating a graphite body containing metallic and ceramic particles
US3293332A (en) * 1962-04-13 1966-12-20 Atomic Energy Authority Uk Process for fabricating a fission product retentive nuclear fuel body
US3173973A (en) * 1962-12-06 1965-03-16 Brockway Marion Clifford Graphite dispersion
US3141911A (en) * 1963-03-20 1964-07-21 Joseph J Hauth Process for the fabrication of nuclear fuel elements
US3284314A (en) * 1963-09-05 1966-11-08 Nukem Gmbh Fuel material for nuclear reactors and process and apparatus for its manufacture
US3274068A (en) * 1964-05-05 1966-09-20 Stanley L Koutz Fuel element
US3344211A (en) * 1964-10-30 1967-09-26 Methods of forming nuclear fuel bodies

Cited By (7)

* Cited by examiner, † Cited by third party
Publication number Priority date Publication date Assignee Title
US3668284A (en) * 1968-04-22 1972-06-06 Atomic Energy Authority Uk Manufacture of nuclear fuel elements
US3708559A (en) * 1970-03-27 1973-01-02 Atomic Energy Authority Uk Method of making nuclear fuel-containing bodies
FR2134518A1 (oth) * 1971-04-28 1972-12-08 Euratom
US3900317A (en) * 1973-03-06 1975-08-19 Canadian Patents Dev Fe-sn-cu-pb sintered composite metal article and process
US4035452A (en) * 1975-01-21 1977-07-12 General Atomic Company Method of making nuclear fuel bodies
US4073834A (en) * 1975-03-05 1978-02-14 General Atomic Company Method of making nuclear fuel elements
DE3704167C1 (de) * 1987-02-11 1988-08-18 Hobeg Hochtemperaturreaktor Verfahren zum Umhuellen von Granuliergut

Also Published As

Publication number Publication date
LU53454A1 (oth) 1967-06-19
CH454292A (de) 1968-04-15
GB1134117A (en) 1968-11-20
DE1589725A1 (de) 1970-05-14
AT273316B (de) 1969-08-11
NL6706058A (oth) 1967-10-30
DE1589725B2 (de) 1975-06-19
BE697093A (oth) 1967-09-18

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