US2863814A - Neutronic reactor fuel element - Google Patents
Neutronic reactor fuel element Download PDFInfo
- Publication number
- US2863814A US2863814A US311574A US31157452A US2863814A US 2863814 A US2863814 A US 2863814A US 311574 A US311574 A US 311574A US 31157452 A US31157452 A US 31157452A US 2863814 A US2863814 A US 2863814A
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- US
- United States
- Prior art keywords
- jacket
- fuel element
- uranium
- coating
- fuel
- 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 - Lifetime
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Classifications
-
- 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
- G21C3/041—Means for removal of gases from fuel elements
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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
- Y10S428/00—Stock material or miscellaneous articles
- Y10S428/922—Static electricity metal bleed-off metallic stock
- Y10S428/9265—Special properties
- Y10S428/933—Sacrificial 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
-
- 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
- Y10T428/12826—Group VIB metal-base component
Definitions
- This invention relates to a fuel element for neutronic reactors. More particularly it pertains to capillary tubes havlng thin walls with an interior coating of material containing an isotope tissionable by neutrons of thermal energy, e. g., Pu239, U235 and H233.
- the objectives in the design of a fuel element are (l) the removal of heat from the fuel by a coolant, (2) the prevention of contamination of the coolant by fission products, and (3) the prevention of migration of fuel particles in the reactor.
- This invention is directed primarily to the last objective. As the fission process occurs, a combination of fission products and minute particles of fissionable material tend to separate from the main body of fuel and migrate away. To minimize this tendency, it is proposed that a very small hollow element be used in great numbers, said hollow element having a fuel coating therein and being completely sealed. Any migration that does occur within such element is thereby rendered immaterial.
- Figure 1 is a vertical sectional view of the fuel element of this invention.
- Figure 2 is a cross sectional view taken on the line 2-2 of Figure 1.
- a fuel element constituting one embodiment of this invention is generally indicated at 4. It is an elongated, cylindrical body having an exterior jacket 6.
- the jacket 6 may be fabricated from a segment of metal tubing which is sealed in a iiuid-tight manner at each end thereof, such as by Welding.
- a coating 8 of mate rial which is a iissionable isotope, such as U2.
- the interior of the fuel element 4 is occupied by a void space 10 in which the fission products, such as xenon, and particles of fissionable material accumulate.
- the elements By selecting a fuel element small enough, a great nurnber of elements may be used in various geometrical relationships with respect to each other. As shown in Stahls copending application, supra, the elements usually are disposed in an end-to-end relationship within a conduit having a larger inside diameter than the outside di ameter of the element which fact permits the flow of a liquid coolant, such as sodium, through the conduit.
- a liquid coolant such as sodium
- Fabrication of the fuel element involved consists of various factors. Metals molybdenum, titanium and zirconium in the form of tubing are satisfactory. A body of U235-enriched uranium in the form of a wire is placed into the capillary tube 6 and both ends of the tube or jacket are sealed in an inert atmosphere. After sealing, the fuel element 4 is heated to a temperature of l250 C. which temperature is above the melting point of uranium. The element 4 is then spun at a high rate of speed, such as 2200 R. P. M., causing a coating 8 of the uranium to cover the entire interior of the jacket. In addition to spinning, the fuel element 4 may be agitated or tumbled in order to secure the coverage of the entire inner surface of the jacket 6.
- the fuel ement is then held at this elevated temperature until a bond is formed between the jacket 6 and the coating 8.
- the metals molybdenum, titanium and zirconium were found to be particularly desirable because they form a boundary alloy with the uranium without the formation of brittle or hard compounds which would tend to scale or ake off during subsequent use in a reactor.
- the dimensions of the uranium body inserted into the tubing can be varied widely and it is clear that the larger the body the thicker the final coating 8.
- Molybdenum is preferred because of its low neutron absorption especially when compared with stainless steel.
- the thermal conductivity of molybdenum is roughly iive times that of stainless steel and its strength is appreciably higher at elevated temperatures. This fact allows for higher unit heat fluxes without producing unsafe stresses.
- tubing or jackets 6 are 0.06" I. D. and 0.08" O. D.
- the lengths can vary Widely, e. g., from 1" to 20".
- a fuel element comprising a duid-tight jacket of a metal of the group consisting of titanium, zirconium,
- vand molybdenum land a coating of U235-enricl1ed uranium on the inner surface of the jacket.
- a fuel element comprising an elongated fluid-tight jacket of titanium, and a coating of U235-enriched uranium on the inner surface of the jacket.
- a fuel element comprising an elongated fluid-tight jacket of zirconium, and a coating of U235-enriched uranium on the inner surface of the jacket.
- a fuel element comprising an'elongated Huid-tight jacket of molybdenum, anii a coating of U235-enriched uranium on the inner surface of the jacket.
- a f'elveleme'nt comprisingI anv'el'ongate'd liu'id-tigilt ⁇ jacket of molybdenum having an inside diameter of 0.060
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- Physics & Mathematics (AREA)
- Engineering & Computer Science (AREA)
- Plasma & Fusion (AREA)
- General Engineering & Computer Science (AREA)
- High Energy & Nuclear Physics (AREA)
- Inorganic Compounds Of Heavy Metals (AREA)
Description
Patented Dec. 9, 1958 z,s63,s14
NEUTRoNIc REAcToR FUEL ELEMENT Kenneth A. KesselringLSchenectady, and Alan U. Seybolt, Scotia, N. Y., assignors to the United States of America as represented by the United States Atomic Energy Commission Application September 26, 1952, Serial No. 311,574
Claims. (Cl. 204-193.2)
This invention relates to a fuel element for neutronic reactors. More particularly it pertains to capillary tubes havlng thin walls with an interior coating of material containing an isotope tissionable by neutrons of thermal energy, e. g., Pu239, U235 and H233.
The objectives in the design of a fuel element are (l) the removal of heat from the fuel by a coolant, (2) the prevention of contamination of the coolant by fission products, and (3) the prevention of migration of fuel particles in the reactor.
This invention is directed primarily to the last objective. As the fission process occurs, a combination of fission products and minute particles of fissionable material tend to separate from the main body of fuel and migrate away. To minimize this tendency, it is proposed that a very small hollow element be used in great numbers, said hollow element having a fuel coating therein and being completely sealed. Any migration that does occur within such element is thereby rendered immaterial.
Since this invention is concerned with the structure and manufacture of very small fuel elements, rather than with the operation of a neutronic reactor, reference is made to U. S. Patent 2,708,656, issued to Enrico Fermi and Leo Szilard, on May 17, 1955.
For a better understanding of the invention7 reference is made to the following description and the appended drawing in which:
Figure 1 is a vertical sectional view of the fuel element of this invention; and
Figure 2 is a cross sectional view taken on the line 2-2 of Figure 1.
The use in a reactor of a great number of small fuel elements satisfies the migration problem. Reference is made to Figures l and 2. A fuel element constituting one embodiment of this invention is generally indicated at 4. It is an elongated, cylindrical body having an exterior jacket 6. The jacket 6 may be fabricated from a segment of metal tubing which is sealed in a iiuid-tight manner at each end thereof, such as by Welding. On the interior 4surface of the jacket 6 is a coating 8 of mate rial which is a iissionable isotope, such as U2. The interior of the fuel element 4 is occupied by a void space 10 in which the fission products, such as xenon, and particles of fissionable material accumulate.
As the fission process proceeds, fission gases and great quantities of heat are evolved. This presents a dual problem of providing a jacket material which is thick enough to withstand the internal pressure of the accumulating gases and which is thin enough to conduct away the heat present on the exterior surface of the element 4.
Fortunately, very small diameter cylinders are good pressure vessels because the ratio of diameter to wall thickness is small. Since the wall thickness of small diameter cylinders can be very thin, it is evident that the removal of heat or thermal energy is also achieved satisfactorily, that is, there is a lower temperature drop across the jacket or wall resulting in less stress than with a thicker walled cylinder.
By selecting a fuel element small enough, a great nurnber of elements may be used in various geometrical relationships with respect to each other. As shown in Stahls copending application, supra, the elements usually are disposed in an end-to-end relationship within a conduit having a larger inside diameter than the outside di ameter of the element which fact permits the flow of a liquid coolant, such as sodium, through the conduit.
Fabrication of the fuel element involved consists of various factors. Metals molybdenum, titanium and zirconium in the form of tubing are satisfactory. A body of U235-enriched uranium in the form of a wire is placed into the capillary tube 6 and both ends of the tube or jacket are sealed in an inert atmosphere. After sealing, the fuel element 4 is heated to a temperature of l250 C. which temperature is above the melting point of uranium. The element 4 is then spun at a high rate of speed, such as 2200 R. P. M., causing a coating 8 of the uranium to cover the entire interior of the jacket. In addition to spinning, the fuel element 4 may be agitated or tumbled in order to secure the coverage of the entire inner surface of the jacket 6. The fuel ement is then held at this elevated temperature until a bond is formed between the jacket 6 and the coating 8. The metals molybdenum, titanium and zirconium were found to be particularly desirable because they form a boundary alloy with the uranium without the formation of brittle or hard compounds which would tend to scale or ake off during subsequent use in a reactor. The dimensions of the uranium body inserted into the tubing can be varied widely and it is clear that the larger the body the thicker the final coating 8.
Molybdenum is preferred because of its low neutron absorption especially when compared with stainless steel. In addition, the thermal conductivity of molybdenum is roughly iive times that of stainless steel and its strength is appreciably higher at elevated temperatures. This fact allows for higher unit heat fluxes without producing unsafe stresses.
With the use of titanium and zirconium, no evidence of uranium scaling or of surface oxidation appeared and no difficulties were encountered in spinning the uranium thereon. Examination of control samples of spun uranium-titanium and uranium-zirconium indicated a uniform coating on the inner surface and a solid bond therebetween. Further, the uranium appeared to have penetrated approximately 0.0002 into the jacket walls during the spinning operation.
The preferred dimensions of the tubing or jackets 6 are 0.06" I. D. and 0.08" O. D. The lengths can vary Widely, e. g., from 1" to 20".
Other variations in the fuel element will be apparent and may be made without departing from the spirit and scope of the invention.
We claim:
l. A fuel element comprising a duid-tight jacket of a metal of the group consisting of titanium, zirconium,
vand molybdenum, land a coating of U235-enricl1ed uranium on the inner surface of the jacket.
2. A fuel element comprising an elongated fluid-tight jacket of titanium, and a coating of U235-enriched uranium on the inner surface of the jacket.
3. A fuel element comprising an elongated fluid-tight jacket of zirconium, and a coating of U235-enriched uranium on the inner surface of the jacket.
4. A fuel element comprising an'elongated Huid-tight jacket of molybdenum, anii a coating of U235-enriched uranium on the inner surface of the jacket.
`5. A f'elveleme'nt comprisingI anv'el'ongate'd liu'id-tigilt `jacket of molybdenum having an inside diameter of 0.060
inch and an outside diameter of 0.080 inch, and a coating of U235-enriched uranium on the inner surface of the jacket.
References Cited in the file of this patent UNITED STATES PATENTS Howe Sept. 29, 1925
Claims (1)
1. A FUEL ELEMENT COMPRISING A FLUID-TIGHT JACKET OF A METAL OF THE GROUP CONSISTING OF TITANIUM, ZIRCONIUM, AND MOLYBDENUM, AND A COATING OF U235-ENRICHED URANIUM ON THE INNER SURFACE OF THE JACKET.
Priority Applications (1)
Application Number | Priority Date | Filing Date | Title |
---|---|---|---|
US311574A US2863814A (en) | 1952-09-26 | 1952-09-26 | Neutronic reactor fuel element |
Applications Claiming Priority (1)
Application Number | Priority Date | Filing Date | Title |
---|---|---|---|
US311574A US2863814A (en) | 1952-09-26 | 1952-09-26 | Neutronic reactor fuel element |
Publications (1)
Publication Number | Publication Date |
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US2863814A true US2863814A (en) | 1958-12-09 |
Family
ID=23207506
Family Applications (1)
Application Number | Title | Priority Date | Filing Date |
---|---|---|---|
US311574A Expired - Lifetime US2863814A (en) | 1952-09-26 | 1952-09-26 | Neutronic reactor fuel element |
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US (1) | US2863814A (en) |
Cited By (9)
Publication number | Priority date | Publication date | Assignee | Title |
---|---|---|---|---|
US3039948A (en) * | 1958-03-14 | 1962-06-19 | Krucoff Darwin | Nuclear reactor with powdered fuel |
US3056737A (en) * | 1958-01-28 | 1962-10-02 | Dow Chemical Co | Neutron amplifier |
US3091581A (en) * | 1958-03-03 | 1963-05-28 | Martin Marietta Corp | Fissionable fuel capsules and method of manufacturing same |
US3098809A (en) * | 1957-08-16 | 1963-07-23 | Huet Andre | Nuclear reactor with fuel under spheroidal form |
US3192621A (en) * | 1959-07-10 | 1965-07-06 | Rolls Royce | Fuel elements for nuclear reactors |
US3211626A (en) * | 1959-12-03 | 1965-10-12 | Westinghouse Electric Corp | Neutronic reactor fuel element and member therefor |
DE1202910B (en) * | 1963-05-07 | 1965-10-14 | Nukem Gmbh | Spherical fuel element for high-temperature power nuclear reactors |
DE1207022B (en) * | 1960-04-21 | 1965-12-16 | Commissariat Energie Atomique | Nuclear reactor fuel element |
US3304234A (en) * | 1956-09-19 | 1967-02-14 | Westinghouse Electric Corp | Fuel element for nuclear reactors |
Citations (3)
Publication number | Priority date | Publication date | Assignee | Title |
---|---|---|---|---|
US1555578A (en) * | 1923-11-06 | 1925-09-29 | Gen Electric | Treatment of metals |
US1730087A (en) * | 1924-04-22 | 1929-10-01 | Daimler Co Ltd | Coating internally of hollow articles with metal |
US2121393A (en) * | 1935-07-04 | 1938-06-21 | Braun Matthaus | Method for coppering of seamless tubes |
-
1952
- 1952-09-26 US US311574A patent/US2863814A/en not_active Expired - Lifetime
Patent Citations (3)
Publication number | Priority date | Publication date | Assignee | Title |
---|---|---|---|---|
US1555578A (en) * | 1923-11-06 | 1925-09-29 | Gen Electric | Treatment of metals |
US1730087A (en) * | 1924-04-22 | 1929-10-01 | Daimler Co Ltd | Coating internally of hollow articles with metal |
US2121393A (en) * | 1935-07-04 | 1938-06-21 | Braun Matthaus | Method for coppering of seamless tubes |
Cited By (9)
Publication number | Priority date | Publication date | Assignee | Title |
---|---|---|---|---|
US3304234A (en) * | 1956-09-19 | 1967-02-14 | Westinghouse Electric Corp | Fuel element for nuclear reactors |
US3098809A (en) * | 1957-08-16 | 1963-07-23 | Huet Andre | Nuclear reactor with fuel under spheroidal form |
US3056737A (en) * | 1958-01-28 | 1962-10-02 | Dow Chemical Co | Neutron amplifier |
US3091581A (en) * | 1958-03-03 | 1963-05-28 | Martin Marietta Corp | Fissionable fuel capsules and method of manufacturing same |
US3039948A (en) * | 1958-03-14 | 1962-06-19 | Krucoff Darwin | Nuclear reactor with powdered fuel |
US3192621A (en) * | 1959-07-10 | 1965-07-06 | Rolls Royce | Fuel elements for nuclear reactors |
US3211626A (en) * | 1959-12-03 | 1965-10-12 | Westinghouse Electric Corp | Neutronic reactor fuel element and member therefor |
DE1207022B (en) * | 1960-04-21 | 1965-12-16 | Commissariat Energie Atomique | Nuclear reactor fuel element |
DE1202910B (en) * | 1963-05-07 | 1965-10-14 | Nukem Gmbh | Spherical fuel element for high-temperature power nuclear reactors |
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