[go: up one dir, main page]

USRE27242E - Fuel element - Google Patents

Fuel element Download PDF

Info

Publication number
USRE27242E
USRE27242E US27242DE USRE27242E US RE27242 E USRE27242 E US RE27242E US 27242D E US27242D E US 27242DE US RE27242 E USRE27242 E US RE27242E
Authority
US
United States
Prior art keywords
envelope
fuel
casing
plastic material
gaps
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
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 filed Critical
Application granted granted Critical
Publication of USRE27242E publication Critical patent/USRE27242E/en
Expired legal-status Critical Current

Links

Images

Classifications

    • 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
    • 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
    • G21C21/06—Manufacture of fuel elements or breeder elements contained in non-active casings by rotatable swaging of the jacket around the fuel
    • 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
    • G21C21/12—Manufacture of fuel elements or breeder elements contained in non-active casings by hydrostatic or thermo-pneumatic canning in general by pressing without lengthening, e.g. explosive coating
    • 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
    • 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
    • Y10T29/49861—Sizing mating parts during final positional association

Definitions

  • FIG. 5 is a diagrammatic representation of FIG. 5.
  • ABSTRACT OF THE DISCLOSURE This invention pertains to an improved method for manufacturing fuel elements for nuclear reactors by surrounding the fuel elements with an envelope of synthetic plastic material and thereafter applying deformation forces to the synthetic plastic envelope in order todecrease or completely remove any gaps existing between the nuclear fuel material and its surrounding casing.
  • a classical fuel element for nuclear reactors is generally composed of nuclear fuel used in any known form as for instance in the form of pellets, spheres, powders, or grains-surrounded by a metallic canning or cladding.
  • the present invention has for its objects a new method that is intended to reduce or eliminate any gaps which may exist between the casing and the nuclear fuel in a fuel element.
  • the method according to the invention consists in applying a pressure to the canning of a fuel element through the instrumentality of a plastic material. This method permits the can to be spaced very closely against the fuel by the use of simple means that are not cumbersome and which require only elementary equipment.
  • the method according to the present invention offers in addition the advantage of enabling the use of a nonisostatic deformation force in order to obtain very good results, in particular with respect to the improvement in heat transfer.
  • the method of the invention has the further advantage that it clamps the canning closely around the fuel so as to reduce relative movement between them. This constitutes an important safety factor for nuclear reactors, and especially for fast breeders.
  • FIGURE 1 is a cross sectional view of a typical type of fuel element to which this invention is applicable.
  • FIGURES 2 through 5 are fragmentary cross sectional views of a fuel element as it goes through the sequence of steps taught by this invention.
  • this fuel element comprises a head portion 7, a foot portion 6, and intermediate the head and foot is a case 12 (of adequate mechanical resistance) which contains nuclear fuel 10 (such as the oxides and carbides of uranium and/or plutonium).
  • the nuclear fuel 10 may be in the form of pellets or in the form of a solid block, and is maintained in the desired position within the casing 12 by means of plugs 8 and 9.
  • the casing 12 may consist of stainless steel, zircalloy, high nickel alloys, niobium and molybdenum alloys, and the like. The preferred thickness is between about 0.2 and 0.8 mm.
  • FIGURE 2 is a cross sectional view which illustrates that even though the casing 112 closely surrounds the nuclear fuel 10, a number of gaps can exist and these gaps do constitute a significant barrier to the transfer of heat from the nuclear fuel 10 to the casing 12 and the surrounding cooling medium.
  • the arrangement shown in FIGURE 2 is surrounded by an envelope of plastic material 14.
  • the plastic material may for instance be a polyvinyl chloride resin, polyvinylidene chloride resin, a polystyrene resin, a polyester resin, a polyamide resin, a polyether resin, a polyurethane resin, or the like, and although the thickness of the plastic envelope is not critical, a thickness of between 1 and 2 millimeters is preferred.
  • Non-isostatic deformation forces such as forging (hammering, rotary swaging) may thereafter be applied to plastic envelope 14 and, since the plastic envelope is not very compressible, the applied deformation force will be transmitted rather uni formly to the casing.
  • the envelope of plastic material is removed from around the casing 12 (e.g. by stripping) and the thus-treated fuel element would appear as is shown in FIGURE 5, containing practically no gaps, as can easily be seen by contrasting FIGURES 2 and 3.
  • the casing 12 with synthetic resin in a number of different ways.
  • the synthetic plastic material is in tubular form it can be simply slipped over the casing 12.
  • strips of plastic material could be wound helically around the casing 12.
  • the casing could be dipped one or more times in molten plastic or sprayed with liquid plastic which would thereafter solidify.
  • the fuel element in the form shown in FIGURE 2 (containing gaps 8) is first surrounded by an envelope of plastic material 14 and then further surrounded by the metallic tube 16 (made of iron, copper, alloys, or the like and about .2 mm. thick) as is shown in FIGURE 4.
  • This assembly is then subjected to the same sort of mechanical deformation treatment (such as forging, hammering, rotary swaging) as was previously described, and the applied, localized deformation forces are transmitted uniformly tothe casing 12 through the plastic envelope 14 to thus reduce or eliminate gaps.
  • the metallic tube 16 and the plastic material 14 are removed (as by stripping or cutting) and the resulting fuel element will appear as is shown in FIGURE 5, having either no gaps or a greatly reduced number of gaps.
  • said synthetic plastic material is selected from the group consisting of polyvinylidene chloride resins, polyvinyl chloride resins, polystyrene resins, polyester resins, polyamide resins, polyetherresins and polyurethane resins.

Landscapes

  • Engineering & Computer Science (AREA)
  • Physics & Mathematics (AREA)
  • Manufacturing & Machinery (AREA)
  • Plasma & Fusion (AREA)
  • General Engineering & Computer Science (AREA)
  • High Energy & Nuclear Physics (AREA)
  • Solid Fuels And Fuel-Associated Substances (AREA)
  • Application Of Or Painting With Fluid Materials (AREA)
  • Fuel-Injection Apparatus (AREA)
  • Monitoring And Testing Of Nuclear Reactors (AREA)
  • Processing And Handling Of Plastics And Other Materials For Molding In General (AREA)

Abstract

THIS INVENTION PERTAINS TO AN IMPROVED METHOD FOR MANUFACTURING FUEL ELEMENTS FOR NUCLEAR REACTORS BY SURROUNDING THE FUEL ELEMENTS WITH AN ENVELOPE OF SYNTHETIC PLASTIC MATERIAL AND THEREAFTER APPLYING DEFORMATION FORCES TO THE SYNTHETIC PLASTIC ENVELOPE IN ORDER TO DE-

CREASE OR COMPLETELY REMOVE ANY GAPS EXISTING BETWEEN THE NUCLEAR FUEL MATERIAL AND ITS SURROUNDING CASING.

Description

Dec. 14, 1971 L, .J. AERTS ETAL Re. 27,242
FUEL ELEMENT Original Filed March :5, 1967 FIG. 3.
FIG. 2.
FIG
FIG. 5.
FIG. 4.
United States Patent 11 Int. Cl. B23p 17/00, 9/00 U.S. Cl. 29-400 8 Claims Matter enclosed in heavy brackets appears in the original patent but forms no part of this reissue specification; matter printed in italics indicates the additions made by reissue.
ABSTRACT OF THE DISCLOSURE This invention pertains to an improved method for manufacturing fuel elements for nuclear reactors by surrounding the fuel elements with an envelope of synthetic plastic material and thereafter applying deformation forces to the synthetic plastic envelope in order todecrease or completely remove any gaps existing between the nuclear fuel material and its surrounding casing.
BACKGROUND A classical fuel element for nuclear reactors is generally composed of nuclear fuel used in any known form as for instance in the form of pellets, spheres, powders, or grains-surrounded by a metallic canning or cladding.
It is known that such a canning often does not exactly fit the fuel, thus giving rise to one or more gaps which can constitute a significant barrier to the transfer of heat between the fuel and the coolant. In order to reduce such gaps, the classical treatment of fuel elements generally involves the application of an isostatic pressure on the fuel elements. However, this is not satisfactory because it requires expensive equipment and complicated manipulation.
BRIEF SUMMARY OF THE INVENTION The present invention has for its objects a new method that is intended to reduce or eliminate any gaps which may exist between the casing and the nuclear fuel in a fuel element.
The method according to the invention consists in applying a pressure to the canning of a fuel element through the instrumentality of a plastic material. This method permits the can to be spaced very closely against the fuel by the use of simple means that are not cumbersome and which require only elementary equipment.
The method according to the present invention offers in addition the advantage of enabling the use of a nonisostatic deformation force in order to obtain very good results, in particular with respect to the improvement in heat transfer.
The method of the invention has the further advantage that it clamps the canning closely around the fuel so as to reduce relative movement between them. This constitutes an important safety factor for nuclear reactors, and especially for fast breeders.
BRIEF DESCRIPTION OF THE SEVERAL VIEWS OF THE INVENTION FIGURE 1 is a cross sectional view of a typical type of fuel element to which this invention is applicable.
FIGURES 2 through 5 are fragmentary cross sectional views of a fuel element as it goes through the sequence of steps taught by this invention.
DETAILED DESCRIPTION Referring now to FIGURE 1, it will be seen that this fuel element comprises a head portion 7, a foot portion 6, and intermediate the head and foot is a case 12 (of adequate mechanical resistance) which contains nuclear fuel 10 (such as the oxides and carbides of uranium and/or plutonium). The nuclear fuel 10 may be in the form of pellets or in the form of a solid block, and is maintained in the desired position within the casing 12 by means of plugs 8 and 9. The casing 12 may consist of stainless steel, zircalloy, high nickel alloys, niobium and molybdenum alloys, and the like. The preferred thickness is between about 0.2 and 0.8 mm.
FIGURE 2 is a cross sectional view which illustrates that even though the casing 112 closely surrounds the nuclear fuel 10, a number of gaps can exist and these gaps do constitute a significant barrier to the transfer of heat from the nuclear fuel 10 to the casing 12 and the surrounding cooling medium.
According to the first embodiment of my invention, the arrangement shown in FIGURE 2 is surrounded by an envelope of plastic material 14. The plastic material may for instance be a polyvinyl chloride resin, polyvinylidene chloride resin, a polystyrene resin, a polyester resin, a polyamide resin, a polyether resin, a polyurethane resin, or the like, and although the thickness of the plastic envelope is not critical, a thickness of between 1 and 2 millimeters is preferred. Non-isostatic deformation forces, such as forging (hammering, rotary swaging) may thereafter be applied to plastic envelope 14 and, since the plastic envelope is not very compressible, the applied deformation force will be transmitted rather uni formly to the casing. After this mechanical treatment, the envelope of plastic material is removed from around the casing 12 (e.g. by stripping) and the thus-treated fuel element would appear as is shown in FIGURE 5, containing practically no gaps, as can easily be seen by contrasting FIGURES 2 and 3.
It will be obvious to those skilled in this art that it is possible to envelope the casing 12 with synthetic resin in a number of different ways. For example, if the synthetic plastic material is in tubular form it can be simply slipped over the casing 12. Alternatively, strips of plastic material could be wound helically around the casing 12. It is also conceivable that the casing could be dipped one or more times in molten plastic or sprayed with liquid plastic which would thereafter solidify.
According to a second embodiment of our invention, the fuel element in the form shown in FIGURE 2, (containing gaps 8) is first surrounded by an envelope of plastic material 14 and then further surrounded by the metallic tube 16 (made of iron, copper, alloys, or the like and about .2 mm. thick) as is shown in FIGURE 4. This assembly is then subjected to the same sort of mechanical deformation treatment (such as forging, hammering, rotary swaging) as was previously described, and the applied, localized deformation forces are transmitted uniformly tothe casing 12 through the plastic envelope 14 to thus reduce or eliminate gaps. Following this mechanical treatment, the metallic tube 16 and the plastic material 14 are removed (as by stripping or cutting) and the resulting fuel element will appear as is shown in FIGURE 5, having either no gaps or a greatly reduced number of gaps.
In conclusion, while the foregoing specification and drawing describe the construction, of preferred embodiments of the instant invention, it is to be understood that ave do not intend to limit ourselves to the precise con- :tructions and arrangements herein disclosed, since the various details of construction, form and arrangement nay obviously be varied to a considerable extent by tnyone skilled in the art without really departing from :he basic principles and novel teachings of this invention 1nd without sacrificing any of the advantages of the in- Iention, and accordingly it is intended to encompass all :hanges, variations, modifications and equivalents falling within the scope of the appended claims.
What is claimed is:
:1. A method for reducing any gaps between the easng and the fuel material in a nuclear fuel element which :omprises:
(a) surrounding the casing with an envelope of synthetic plastic material,
(b) applying a non-isostatic deformation force to the assembly set forth in (a), and
(c) removing the envelope of synthetic plastic material.
2. A method according to claim 1, wherein the applied leformation pressure is non-isostatic pressure.
3. A method according to claim 11, wherein said dei'ormation pressure is exerted by forging.
4. A method according to claim 1, wherein the de- Formation force is applied by hammering.
5. A method according to claim 1, wherein said pres- .ure is applied by rotary swaging.
6. A method according to claim 1, wherein said synthetic plastic material is selected from the group consisting of polyvinylidene chloride resins, polyvinyl chloride resins, polystyrene resins, polyester resins, polyamide resins, polyetherresins and polyurethane resins.
7. A claim according to claim 1, wherein the envelope of synthetic plastic material is in turn surrounded by a metallic envelope prior to the application of the deformation force.
8. A claim according to claim 1, wherein the thickness of said envelope of synthetic plastic material is between about 1 and 2 mm.
References Cited The following references, cited by the Examiner, are of record in the patented file of this patent or the original patent.
UNITED STATES PATENTS 3,100,742 8/1963 McGeary et al 29480 3,291,870 12/ 1966 Allison 29--423 3,089,830 5/1963 McGeary et a1 29-445 3,192,621 7/1965 Bauer et a1. 2942 X THOMAS H. EAGER, Primary Examiner US. Cl. X.R. 29-423, 445
US27242D 1966-03-04 1970-08-10 Fuel element Expired USRE27242E (en)

Applications Claiming Priority (2)

Application Number Priority Date Filing Date Title
BE24811 1966-03-04
US62048967A 1967-03-03 1967-03-03

Publications (1)

Publication Number Publication Date
USRE27242E true USRE27242E (en) 1971-12-14

Family

ID=25647053

Family Applications (2)

Application Number Title Priority Date Filing Date
US620489A Expired - Lifetime US3488827A (en) 1966-03-04 1967-03-03 Fuel element
US27242D Expired USRE27242E (en) 1966-03-04 1970-08-10 Fuel element

Family Applications Before (1)

Application Number Title Priority Date Filing Date
US620489A Expired - Lifetime US3488827A (en) 1966-03-04 1967-03-03 Fuel element

Country Status (5)

Country Link
US (2) US3488827A (en)
BE (1) BE677348A (en)
DE (1) DE1614438A1 (en)
FR (1) FR1512048A (en)
NL (1) NL6702680A (en)

Families Citing this family (1)

* Cited by examiner, † Cited by third party
Publication number Priority date Publication date Assignee Title
US3756053A (en) * 1972-05-01 1973-09-04 Teledyne Inc Method for bending tubes

Family Cites Families (3)

* Cited by examiner, † Cited by third party
Publication number Priority date Publication date Assignee Title
NL237134A (en) * 1958-03-17
GB937660A (en) * 1959-07-10 1963-09-25 Rolls Royce Improvements in or relating to fuel elements for nuclear reactors
US3291870A (en) * 1964-06-12 1966-12-13 George S Allison Method of fabricating a multichannel nuclear fuel element

Also Published As

Publication number Publication date
DE1614438A1 (en) 1970-07-02
BE677348A (en) 1966-09-05
NL6702680A (en) 1967-09-05
US3488827A (en) 1970-01-13
FR1512048A (en) 1968-02-02

Similar Documents

Publication Publication Date Title
US3089830A (en) Method of making a compartmented fuel element for a nuclear reactor
US3230150A (en) Metal-clad fuel element with copper foil interlayer
EP0611614A1 (en) Device for forming a mechanical connection between two concentric tubes
USRE27242E (en) Fuel element
DE1200965B (en) Nuclear reactor fuel element
US3245140A (en) Fabrication of oxide fuel elements by rotary swaging
US3087879A (en) Control rod
DE1232279B (en) Device for increasing the burn-through heat flow in boiling water nuclear reactors
US3105037A (en) Concentric tube fuel element spring alignment spacer device
DE60303737T2 (en) Thermoacoustic wave generator
US3415911A (en) Fuel element fabrication
GB1085383A (en) Improvements in or relating to fuel pencils having a thin flexible can, for nuclear reeactors
AT220257B (en) Process for the production of ceramic fuel elements
DE2459104C3 (en) Process for making a cooled magnet winding
DE1160560B (en) Device for monitoring nuclear reactor fuel elements
DE2034549B2 (en) Fuel assembly for nuclear reactors
DE3306748A1 (en) FUEL STICK FOR CORE REACTORS
CH623174A5 (en)
AT270008B (en) Fuel element, especially for water-cooled or metal-cooled nuclear reactors
AT368825B (en) METHOD AND DEVICE FOR INDUCTIVE HEATING OF A METAL WORKPIECE
DE1207022B (en) Nuclear reactor fuel element
DE2126984A1 (en) Electric tubular heater
DE1614308C3 (en) Rod-shaped fuel assembly for nuclear reactors
DE1614292A1 (en) Isotopic heat generator
DE1764323C3 (en) Irradiation skaps I