US2947080A - Method for making fuel elements - Google Patents
Method for making fuel elements Download PDFInfo
- Publication number
- US2947080A US2947080A US334102A US33410253A US2947080A US 2947080 A US2947080 A US 2947080A US 334102 A US334102 A US 334102A US 33410253 A US33410253 A US 33410253A US 2947080 A US2947080 A US 2947080A
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- wire
- fuel elements
- zirconium
- cladding
- core material
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- 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
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- 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
-
- 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
- Y10—TECHNICAL SUBJECTS COVERED BY FORMER USPC
- Y10S—TECHNICAL SUBJECTS COVERED BY FORMER USPC CROSS-REFERENCE ART COLLECTIONS [XRACs] AND DIGESTS
- Y10S376/00—Induced nuclear reactions: processes, systems, and elements
- Y10S376/90—Particular material or material shapes for fission reactors
- Y10S376/901—Fuel
- Y10S376/902—Fuel with external lubricating or absorbing material
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- 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
- Y10—TECHNICAL SUBJECTS COVERED BY FORMER USPC
- Y10T—TECHNICAL SUBJECTS COVERED BY FORMER US CLASSIFICATION
- Y10T29/00—Metal working
- Y10T29/49—Method of mechanical manufacture
- Y10T29/4981—Utilizing transitory attached element or associated separate material
-
- 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
- Y10—TECHNICAL SUBJECTS COVERED BY FORMER USPC
- Y10T—TECHNICAL SUBJECTS COVERED BY FORMER US CLASSIFICATION
- Y10T29/00—Metal working
- Y10T29/49—Method of mechanical manufacture
- Y10T29/49826—Assembling or joining
-
- 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
- Y10—TECHNICAL SUBJECTS COVERED BY FORMER USPC
- Y10T—TECHNICAL SUBJECTS COVERED BY FORMER US CLASSIFICATION
- Y10T29/00—Metal working
- Y10T29/49—Method of mechanical manufacture
- Y10T29/49826—Assembling or joining
- Y10T29/49863—Assembling or joining with prestressing of part
- Y10T29/49865—Assembling or joining with prestressing of part by temperature differential [e.g., shrink fit]
-
- 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
- Y10—TECHNICAL SUBJECTS COVERED BY FORMER USPC
- Y10T—TECHNICAL SUBJECTS COVERED BY FORMER US CLASSIFICATION
- Y10T428/00—Stock material or miscellaneous articles
- Y10T428/12—All metal or with adjacent metals
- Y10T428/12486—Laterally noncoextensive components [e.g., embedded, etc.]
-
- 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
- Y10—TECHNICAL SUBJECTS COVERED BY FORMER USPC
- Y10T—TECHNICAL SUBJECTS COVERED BY FORMER US CLASSIFICATION
- Y10T428/00—Stock material or miscellaneous articles
- Y10T428/12—All metal or with adjacent metals
- Y10T428/12493—Composite; i.e., plural, adjacent, spatially distinct metal components [e.g., layers, joint, etc.]
- Y10T428/12771—Transition metal-base component
-
- 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
- Y10—TECHNICAL SUBJECTS COVERED BY FORMER USPC
- Y10T—TECHNICAL SUBJECTS COVERED BY FORMER US CLASSIFICATION
- Y10T428/00—Stock material or miscellaneous articles
- Y10T428/12—All metal or with adjacent metals
- Y10T428/12493—Composite; i.e., plural, adjacent, spatially distinct metal components [e.g., layers, joint, etc.]
- Y10T428/12771—Transition metal-base component
- Y10T428/12806—Refractory [Group IVB, VB, or VIB] metal-base component
Definitions
- This invention relates to a method for making fuel elements. More particularly, it relates to a method for making fuel elements for a nuclear type reactor.
- Figure l is a sectional elevation showing the component parts of the fuel element in the initial stages of its fabrication.
- wire-like, or ribbon-like fuel elements of predetermined lengths can be attained in a commercial manner by introducing measured quantities of core material into a hollow tube whose cross section is not necessarily round and which is made of cladding material by alternately introducing measured quantities of core material and a plug made up of these same compositions as the cladding material into a hollow tube of clad material and sealing off the ends of the hollow tube, drawing or otherwise working the clad tubing down into the desired dimensional size and finally cutting the wire so formed into the desired lengths by cutting through those sections-Where the plug material is present.
- the components which go into making the wire-like fuel elements of this invention can naturally be the same Unite ttes Patent 2,947,080 P atented Aug. 2, 1960 ice type metals which are normally used in making fuel elements for nuclear reactions.
- the cladding material 10 should naturally be made out of a corrosion resistant metal since different types of nuclear reactors operate under different conditions and with the use of different cooling mediums the material used for this purpose can of course vary over a rather wide range.
- the preferred material to be used is normally one having a low neutron absorption cross section and which is corrosion resistant to water and air.
- metal such as zirconium, beryllium and aluminum are preferred examples.
- metals having a higher neutron absorption cross section may be used.
- Stainless steel is a good example of such material.
- the important characteristic of course is the metals corrosion resistance.
- the metal which is used to make the sheathing material 16 must, of course, be one which is chosen because of its characteristics. Its function is to prevent the oxidation of the cladding material during the processing of the composite that is during the rolling, swaging or drawing operations during which the Wire or ribbon is being formed.
- This material must be one which can withstand rather high temperatures but one which will not enter into a reaction with the cladding material so that at the temperatures at which the material is worked it neither alloys therewith nor forms brittle mixtures which will make it impossible to work the metal into the desired shape and form.
- the metal should, furthermore, be relatively cheap and one which can readily be removed from the cladding material by physical or chemical means.
- a good example of such material is cold rolled iron particularly when zirconium or zirconium alloy is used as the cladding material. In many of these cases the iron can be removed by dissolving it in an acid solution such as a 50% nitric acid solution.
- g g t The essential features of this invention are, of course, the use of measured quantities of the core material interspersed between plugs of the cladding material within the tubular cladding material itself.
- the sheath components have been prepared in the manner illustrated in Figure 1 and either rolled, swaged or drawn down to the desired size the resulting structure is a continuous wire or ribbon which has alternate cores of fissionable material and separated by plugs of the cladding metal.
- the long single piece of wire can then be cut up into such lengths so that each individual piece will only contain one section of fissionable material as its core and which fissionable corematerial will be completely surrounded by cladding metal both at its side and at the end.
- This can be accomplished by cutting the wire or ribbon at those points at which the cladded'material plugs the wire or ribbon. If equal amounts of fissionable or core material were placed between the individual plugs which 'wentto maketheoriginal composite piece it will be possible to obtain similar size pieces of wire or ribbon in which the core material is completely surrounded by the metal formed by cutting the finished wire at those places at which the plugs separate one section of core material from the other.
- a tube of zirconium or one of its alloys having good corrosion resistant properties and having an outside-diameter of about /2" and an inside diameter of about .250" is plugged at one end with a piece of zirconium of the proper size after which a slug of core material such as, for example, uranium having an outside diameter of .250" after having been cooled in Dry Ice is introduced into the tubular zirconium.
- a slug of core material such as, for example, uranium having an outside diameter of .250" after having been cooled in Dry Ice is introduced into the tubular zirconium.
- a .piece of clad material to form a plug at the top of the core material after which a second section of the cooled core material is placed on top of the plug.
- the sheathing material can be removed. This is preferably done by some chemical means.
- the iron can readily be removed by dissolving it in dilute nitric acid of about 50% nitric acid in Water. By this means the iron will be dissolved but the zirconium will be intact.
- the dimensions of the finished product will of course depend on the amount of working that takes place. .It is readily possible, for example, to obtain wires having an outside dimension of .080" and with a core diameter of .040.
- the method of manufacturing a nuclear fuel element in the form of a wire having a core containing fissionable material in close contact with a cladding metal comprises the steps of plugging one end of a hollow tubeof zirconium with a plug made of zirconium, chilling a slug of uranium in Dry Ice, introducing the chilled slug into the zirconium tube to rest against the plug, ;introducing a second zirconium plug into the tube and in contact with the chilled uranium slug, inserting additional chilled uranium slugs and zirconium plugs alternately into the zirconium tube until the entire length of th tube is filled, permitting the chilled uranium plugs ;to attain room temperature, whereby the uranium will expand into close contact with the zirconium tube, inser ing the filled tube in an iron sheath, working the sheathed tubing ,at a temperature in the range of 600 to 900 C. to form a wire of predetermined diameter
Description
Aug. 2, 1960 L. W. KATES ETAL METHOD FOR MAKING FUEL ELEMENTS Filed Jan. 29; 1955 INVENTORS LEONARD W. KATES ROBERT W. CAMPBELL BRAYMOND HW. HEARTEL lVIETI-IOD FOR MAG FUEL ELEMENTS Leonard W. Kates, Hempstead, and Robert W. Campbell, Malverne, N.Y., and Raymond H. W. Heartel, Cranford, N..I., assignors, by mesne assignments, to the United States of America as represented by the United States Atomic Energy Commission Filed Jan. 29, 1953, Ser. No. 334,102
1 Claim. (Cl. 29528) This invention relates to a method for making fuel elements. More particularly, it relates to a method for making fuel elements for a nuclear type reactor.
Many types of fuel elements have been devised and developed for use in nuclear reactors. Among these are the so-called wire plate and ribbon types. The wire type has an advantage over the other types in that it has a very large ratio of surface area to volume of fuel element. Although methods have previously been devised for making this wire type fuel element none of the prior art methods heretofore used have lent themselves to the manufacture of wire-like or ribbon type fuel elements of a desired length, that is to say, none of the heretofore used methods are adapted to make desired lengths of this fuel element in a commercial manner which require no further fabrication.
It is, therefore, an object of this invention to provide a method of making fuel elements of any desired length by a commercially practical method.
It is a further object of this invention to provide a simple method for making the wire type fuel elements which will permit the manufacture of an indefinite number of predetermined lengths of wire in a continuous manner. It is another object to make cored wire with uncored ends for fastening or joining without necessity of welding or otherwise fabricating the cored material itself.
It has been found that these objects and other advan- I tages incidental thereto can be attained in accordance with this invention.
In the drawings which illustrate features of this invention Figure l is a sectional elevation showing the component parts of the fuel element in the initial stages of its fabrication.
In accordance with this invention it has been found that wire-like, or ribbon-like fuel elements of predetermined lengths can be attained in a commercial manner by introducing measured quantities of core material into a hollow tube whose cross section is not necessarily round and which is made of cladding material by alternately introducing measured quantities of core material and a plug made up of these same compositions as the cladding material into a hollow tube of clad material and sealing off the ends of the hollow tube, drawing or otherwise working the clad tubing down into the desired dimensional size and finally cutting the wire so formed into the desired lengths by cutting through those sections-Where the plug material is present.
The assembly of these components is most aptly shown in Figure 1 of the drawings where indicates the hollow tube of cladding material, 12 the core material, 14 the plugs which have been inserted between the measured quantity of core material and 16 a protective sheathing material which may be used during the actual working down of the metal into its wire form.
The components which go into making the wire-like fuel elements of this invention can naturally be the same Unite ttes Patent 2,947,080 P atented Aug. 2, 1960 ice type metals which are normally used in making fuel elements for nuclear reactions. The cladding material 10 should naturally be made out of a corrosion resistant metal since different types of nuclear reactors operate under different conditions and with the use of different cooling mediums the material used for this purpose can of course vary over a rather wide range. In the so-called slow type reactor the preferred material to be used is normally one having a low neutron absorption cross section and which is corrosion resistant to water and air. For this purpose metal such as zirconium, beryllium and aluminum are preferred examples. In the faster reactors metals having a higher neutron absorption cross section may be used. Stainless steel is a good example of such material. The important characteristic of course is the metals corrosion resistance.
The specific core material which is to be used in making, these wire type fuel elements is also not of any particular or significant importance. Any one of the substances-which is normally used for this purpose such as uranium or its alloys would lend themselves to the making of fuel elements in accordance with this invention.
The metal which is used to make the sheathing material 16 must, of course, be one which is chosen because of its characteristics. Its function is to prevent the oxidation of the cladding material during the processing of the composite that is during the rolling, swaging or drawing operations during which the Wire or ribbon is being formed. This material must be one which can withstand rather high temperatures but one which will not enter into a reaction with the cladding material so that at the temperatures at which the material is worked it neither alloys therewith nor forms brittle mixtures which will make it impossible to work the metal into the desired shape and form. The metal should, furthermore, be relatively cheap and one which can readily be removed from the cladding material by physical or chemical means. A good example of such material is cold rolled iron particularly when zirconium or zirconium alloy is used as the cladding material. In many of these cases the iron can be removed by dissolving it in an acid solution such as a 50% nitric acid solution. g g t The essential features of this invention are, of course, the use of measured quantities of the core material interspersed between plugs of the cladding material within the tubular cladding material itself. When'the sheath components have been prepared in the manner illustrated in Figure 1 and either rolled, swaged or drawn down to the desired size the resulting structure is a continuous wire or ribbon which has alternate cores of fissionable material and separated by plugs of the cladding metal. The long single piece of wire can then be cut up into such lengths so that each individual piece will only contain one section of fissionable material as its core and which fissionable corematerial will be completely surrounded by cladding metal both at its side and at the end. This, of course, can be accomplished by cutting the wire or ribbon at those points at which the cladded'material plugs the wire or ribbon. If equal amounts of fissionable or core material were placed between the individual plugs which 'wentto maketheoriginal composite piece it will be possible to obtain similar size pieces of wire or ribbon in which the core material is completely surrounded by the metal formed by cutting the finished wire at those places at which the plugs separate one section of core material from the other.
The actual determination as to where to cut the finished Wire or ribbon to obtain the desired lengths can of course be accomplished by the trial and error procedure. However, a much simpler and better method is to make use of radiographic equipment for inspecting the wire. With the use of this equipment it is readily possible to determine at which points in the wire or ribbon are the plugs and which points contain the core material.
In those cases in which the core material is sufiiciently active to energize a simple counter this device could of course be used for the same purpose.
By this means it is therefore readily possible to cut the wire at the desired point selected as a result of the radiographic inspection thus making it possible to cut the wire at only those points at which the active core material will be completely surrounded by the cladding metal.
In assembling the components of the Wire preparatory to working it to form the wire by swaging or drawing it is preferable to take steps to make certain of a good bond between the core material and the cladding, if best results are to be obtained. In order to insure a good snug sfit it 'has been found desirable to make a so-called sweat .fit between the core material and the cladding material. This can be accomplished by chilling the core material .in Dry Ice or in Dry Ice in acetone and then inserting it into the tube of cladding material after which the plug materials are inserted and the whole composite is allowed to come up to temperature at which time the core .material will expand and make a snug fit with the cladding material. To accomplish this it is of course necessary that the inside diameter of the cladding material "and the outside diameter of the core are of suitable .di-
-.mensions to make this method of assembly necessary and workable.
The following is an illustrative example of a method vof making a wire in accordance with this method. A tube of zirconium or one of its alloys having good corrosion resistant properties and having an outside-diameter of about /2" and an inside diameter of about .250" is plugged at one end with a piece of zirconium of the proper size after which a slug of core material such as, for example, uranium having an outside diameter of .250" after having been cooled in Dry Ice is introduced into the tubular zirconium. This is followed with a .piece of clad material to form a plug at the top of the core material after which a second section of the cooled core material is placed on top of the plug. This is again followed with a plug and a third section of cooled core material of size similar to the first two. This operation is continued with alternate sections of core material and plugs until the entire tube of cladding material 'has been filled and the plug 14 has been inserted at its outer end. The cored tubulation is then sheathed in a sheathing material such as iron for example whereupon it is ready to be worked to form the wire or ribbon of the desired gauge or size. To obtain best results the working is usually carried on at temperatures lying within the range of 800 to 900 C. However, temperatures as low as 600 C. might also be used. It is, however, best not to exceed 900 C. particularly when using iron as the sheath material and zirconium as the cladding material, since above these temperatures the iron and zirconium will alloy to form a brittle eutectic mixture.
When the composite is held vw'thin a temperature range of about up to 900 C. it can readily be worked either by swaging or drawing to form wire of the desired dimensional characteristics. Naturally some composite materials can be worked more readily than others. The determining factor is, of course, the ductility of the met- 'this manner it is more readily possible to hold the material to the desired quality.
After the material has been Worked to the desired dimension the sheathing material can be removed. This is preferably done by some chemical means. In the case of iron with a zirconium cladding material the iron can readily be removed by dissolving it in dilute nitric acid of about 50% nitric acid in Water. By this means the iron will be dissolved but the zirconium will be intact.
The dimensions of the finished product will of course depend on the amount of working that takes place. .It is readily possible, for example, to obtain wires having an outside dimension of .080" and with a core diameter of .040.
When this wire is obtained it is subjected to radiographic inspection which indicates the plates at which-the plug material separates the fissionable core material from the next succeeding core of fissionable material, whereupon the wire is cut at these points where the plug is present thus yielding as a final product equal lengths of .a wire-type fuel element completely surrounded by a cladding metal. The material thus obtained requires no further fabrication to seal in the core material.
While the above description and drawings submitted herewith disclose a preferred and practical embodiment of the fuel element of this invention it will be understood that the specific details of construction and arrangement of parts as shown and described are by way of i1- lustration and are not to be construed as limiting the scope of the invention.
What is claimed is: p
The method of manufacturing a nuclear fuel element in the form of a wire having a core containing fissionable material in close contact with a cladding metal that comprises the steps of plugging one end of a hollow tubeof zirconium with a plug made of zirconium, chilling a slug of uranium in Dry Ice, introducing the chilled slug into the zirconium tube to rest against the plug, ;introducing a second zirconium plug into the tube and in contact with the chilled uranium slug, inserting additional chilled uranium slugs and zirconium plugs alternately into the zirconium tube until the entire length of th tube is filled, permitting the chilled uranium plugs ;to attain room temperature, whereby the uranium will expand into close contact with the zirconium tube, inser ing the filled tube in an iron sheath, working the sheathed tubing ,at a temperature in the range of 600 to 900 C. to form a wire of predetermined diameter, and thereafter removing the sheath.
References Cited in the file of this patent UNITED STATES PATENTS
Priority Applications (1)
Application Number | Priority Date | Filing Date | Title |
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US334102A US2947080A (en) | 1953-01-29 | 1953-01-29 | Method for making fuel elements |
Applications Claiming Priority (1)
Application Number | Priority Date | Filing Date | Title |
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US334102A US2947080A (en) | 1953-01-29 | 1953-01-29 | Method for making fuel elements |
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Publication Number | Publication Date |
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US2947080A true US2947080A (en) | 1960-08-02 |
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US334102A Expired - Lifetime US2947080A (en) | 1953-01-29 | 1953-01-29 | Method for making fuel elements |
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Cited By (10)
Publication number | Priority date | Publication date | Assignee | Title |
---|---|---|---|---|
US3089830A (en) * | 1958-03-17 | 1963-05-14 | Robert K Mcgeary | Method of making a compartmented fuel element for a nuclear reactor |
US3192621A (en) * | 1959-07-10 | 1965-07-06 | Rolls Royce | Fuel elements for nuclear reactors |
US3245140A (en) * | 1958-05-27 | 1966-04-12 | Babcock & Wilcox Co | Fabrication of oxide fuel elements by rotary swaging |
US3275525A (en) * | 1965-07-20 | 1966-09-27 | Clarence H Bloomster | Nuclear fuel element incorporating helical fissionable wire |
US3276867A (en) * | 1964-05-05 | 1966-10-04 | Daniel W Brite | Cermet materials and process of making |
DE1277171B (en) * | 1963-09-14 | 1968-09-12 | Deutsche Erdoel Ag | Device and method for the thermal and / or chemonuclear treatment of substances underground |
US3753704A (en) * | 1967-04-14 | 1973-08-21 | Int Nickel Co | Production of clad metal articles |
US4080253A (en) * | 1976-09-21 | 1978-03-21 | Westinghouse Electric Corporation | Expandable device for a nuclear fuel rod |
US4486385A (en) * | 1980-03-14 | 1984-12-04 | Nyby Uddeholm Ab | Tubular composite elements processes and a pressing for their production |
US6233299B1 (en) * | 1998-10-02 | 2001-05-15 | Japan Nuclear Cycle Development Institute | Assembly for transmutation of a long-lived radioactive material |
Citations (3)
Publication number | Priority date | Publication date | Assignee | Title |
---|---|---|---|---|
US1615094A (en) * | 1923-01-23 | 1927-01-18 | Western Electric Co | Cored article and method of producing such articles |
US2079710A (en) * | 1934-01-23 | 1937-05-11 | Jaeobson Eugene | Self-fluxing solder and process and apparatus for producing same |
US2293810A (en) * | 1938-06-22 | 1942-08-25 | Nat Standard Co | Electroplating stainless steel |
-
1953
- 1953-01-29 US US334102A patent/US2947080A/en not_active Expired - Lifetime
Patent Citations (3)
Publication number | Priority date | Publication date | Assignee | Title |
---|---|---|---|---|
US1615094A (en) * | 1923-01-23 | 1927-01-18 | Western Electric Co | Cored article and method of producing such articles |
US2079710A (en) * | 1934-01-23 | 1937-05-11 | Jaeobson Eugene | Self-fluxing solder and process and apparatus for producing same |
US2293810A (en) * | 1938-06-22 | 1942-08-25 | Nat Standard Co | Electroplating stainless steel |
Cited By (10)
Publication number | Priority date | Publication date | Assignee | Title |
---|---|---|---|---|
US3089830A (en) * | 1958-03-17 | 1963-05-14 | Robert K Mcgeary | Method of making a compartmented fuel element for a nuclear reactor |
US3245140A (en) * | 1958-05-27 | 1966-04-12 | Babcock & Wilcox Co | Fabrication of oxide fuel elements by rotary swaging |
US3192621A (en) * | 1959-07-10 | 1965-07-06 | Rolls Royce | Fuel elements for nuclear reactors |
DE1277171B (en) * | 1963-09-14 | 1968-09-12 | Deutsche Erdoel Ag | Device and method for the thermal and / or chemonuclear treatment of substances underground |
US3276867A (en) * | 1964-05-05 | 1966-10-04 | Daniel W Brite | Cermet materials and process of making |
US3275525A (en) * | 1965-07-20 | 1966-09-27 | Clarence H Bloomster | Nuclear fuel element incorporating helical fissionable wire |
US3753704A (en) * | 1967-04-14 | 1973-08-21 | Int Nickel Co | Production of clad metal articles |
US4080253A (en) * | 1976-09-21 | 1978-03-21 | Westinghouse Electric Corporation | Expandable device for a nuclear fuel rod |
US4486385A (en) * | 1980-03-14 | 1984-12-04 | Nyby Uddeholm Ab | Tubular composite elements processes and a pressing for their production |
US6233299B1 (en) * | 1998-10-02 | 2001-05-15 | Japan Nuclear Cycle Development Institute | Assembly for transmutation of a long-lived radioactive material |
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