US3384551A - Fuel element heat transfer arrangement - Google Patents

Fuel element heat transfer arrangement Download PDF

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Publication number
US3384551A
US3384551A US528306A US52830666A US3384551A US 3384551 A US3384551 A US 3384551A US 528306 A US528306 A US 528306A US 52830666 A US52830666 A US 52830666A US 3384551 A US3384551 A US 3384551A
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United States
Prior art keywords
fuel element
tube
region
jacket
vapor
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
Application number
US528306A
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English (en)
Inventor
Kornbichler Heinz
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.)
Licentia Patent Verwaltungs GmbH
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Licentia Patent Verwaltungs GmbH
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Publication date
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    • G—PHYSICS
    • G21—NUCLEAR PHYSICS; NUCLEAR ENGINEERING
    • G21C—NUCLEAR REACTORS
    • G21C15/00—Cooling arrangements within the pressure vessel containing the core; Selection of specific coolants
    • G21C15/02—Arrangements or disposition of passages in which heat is transferred to the coolant; Coolant flow control devices
    • G21C15/04—Arrangements or disposition of passages in which heat is transferred to the coolant; Coolant flow control devices from fissile or breeder material
    • G21C15/06—Arrangements or disposition of passages in which heat is transferred to the coolant; Coolant flow control devices from fissile or breeder material in fuel elements
    • 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
    • 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
    • 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
    • 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
    • G21C3/06—Casings; Jackets
    • 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
    • G21C3/06—Casings; Jackets
    • G21C3/10—End closures ; Means for tight mounting therefor
    • 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
    • G21C3/16—Details of the construction within the casing
    • G21C3/20—Details of the construction within the casing with coating on fuel or on inside of casing; with non-active interlayer between casing and active material with multiple casings or multiple active layers
    • 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

  • a cladding arrangement for protecting a tubular fuel element including an inner jacket covering the inner surface of the fuel element, a corrosion resistant metal layer covering the first jacket, a second jacket covering the outer surface of the fuel element, and a sealing plug disposed at each end of the fuel element for sealing off the ends thereof, the jackets and plug all being made of a material having a low ratio of neutron absorption to mechanical strength at the temperatures to which the fuel is to be raised.
  • the present invention relates to the field of heat generation, and particularly to fuel elements for nuclear reactors.
  • the cladding material must meet the following two primary requirements: (1) it must be corrosion-resistant under the normal operating conditions of the reactor; and (2) it must have the smallest possible neutron capture cross section, i.e., the ratio of neutron absorption per unit of volume to the mechanical strength of the cladding should be a small as possible.
  • a more specific object of the present invention is to provide improved cladding for ceramic fuel elements.
  • Still another object of the present invention is to provide a fuel element cladding which has both a high corrosion resistance and a low neutron capture cross section.
  • novel advantages of the present invention are realized by the provision, in connection with a fuel element for heating a primary coolant vapor to a predeter- 3,384,551 Patented May 21, 1968 "ice mined temperature in a reactor, of a cladding arrangement including a first jacket made of a metal having a low ratio of neutron absorption to mechanical strength at temperatures in the region of the predetermined temperature.
  • This jacket covers the surface of the fuel element which is adjacent the region occupied by the primary coolant vapor.
  • a second jacket made of a zirconium alloy fitted around the outer surface of the fuel element for mechanically supporting the same.
  • a sealing plug at each end of the fuel element for sealing off the fuel element, this plug being made of the same material as the jacket and being welded to both the first jacket and the second jacket.
  • Yet another feature of the present invention resides in the provision of a thermal protective cap made of a corrosion-resistant material disposed adjacent that end of the inner jacket through which the primary coolant vapor exits for isolating this end of the jacket and the weld disposed at this end from the heated primary coolant vapor.
  • the figure shows a preferred embodiment of the present invention wherein the fuel element 1, which may be made of uranium dioxide for example, has a tubular configuration and is arranged to be surrounded by a mass of boiling water in the region 2, it being intended that this boiling water be maintained at a temperature of approximately 285 C.
  • the saturated vapor, or steam 3, into which the boiling water in the portion of region 2 adjacent the fuel element is converted by the heat generated in the fuel element is conveyed into the central region 6 within fuel element 1 by any suitable, well-known vapor supplying system (not shown). This vapor is further heated during its passage through the central region of the fuel element and exits from the region 4 as superheated steam.
  • the outer circumference of fuel element 1 is enclosed by an encasing tube 5 made of a suitable zirconium alloy which acts as a mechanical support for the fuel element.
  • the inner surface of the fuel element is isolated from the high temperature vapor in the region 6 by a double tube 7, 8.
  • This double tube consists of a tube 7 which may be made of Zircaloy, for example, and an inner, thin metallic tube or coating 8 which may be made of Incoloy, for example.
  • the coating 8 serves to prevent corrosion of the tube 7. 4
  • th fuel element 1 is provided at each end with an annular sealing plug 9 which is also made, for example, of Zircaloy, and to the inside of which there is disposed a thermal protective cap 10.
  • this protective cap is integral with a further tube portion which serves to convey superheated steam leaving the region 6' of fuel element 1 out of the reactor.
  • a highly satisfactory jacket for the fuel element 1 could be constructed by covering the outer surface of the fuel element with a sheath made of Zircaloy, this material having a low neutron capture level and good corrosion resistance to the boiling water in the region 2, and by covering the inner surface of the fuel element with a sheath made of one of the higher nickel-containing alloys, such as Incoloy, for example, which would have a highly satisfactory corrosion resistance to the superheated vapor present in the region 6.
  • a serious obstacle exists to such a form of construction because of the difficulty of welding zirconium to steel.
  • the welding seam 11 between the layer or tube 8 and the Zircalogy tube 7 need not have any substantial structural strength and serves merely to seal the joint between the tubes 7 and 8 in order to prevent vapor from penetrating into the annular region therebetween. No great difiiculties are encountered in forming such a weld between zirconium and steel, even when the steel is constituted by one of the higher nickel-containing alloys, because, as has been noted above, this weld need not have any substantial structural strength.
  • the thermal protective cap 10 which extends to the inside of, and along, the upper end of the arrangement of tube 7 and tube or coating 8 in order to permit only a small percentage of the superheated steam to reach the region adjacent welds 11 and 12. Because Zircaloy is a good conductor of heat, and because the temperature 'at the outer surface of the arrangement is substantially lower than that in the region 6, it results that the region adjacent the welds 11 and 12 is maintained at a temperature which is not substantially higher than that of the boiling water occupying the region 2. It is known that Zirca loy is highly resistant to corrosion at these temperatures. Because the weld 12 is formed between two bodies of the same material, this weld is capable of withstanding high stresses.
  • this protective cap offers the further advantage that the weld 11 is not subjected to the frequent temperature variations to which the vapor in the region 6 is subjected when the fuel element is cycled between a full :load and a no-load state. Such cycling may often cause the temperature of the vapor in the region 6 to fluctuate between a temperature of 500 C. and a temperature of 300 C., for example. Such cycling often takes place daily and even more frequently in the operation of a power plant.
  • the seam 11 will be subjected to a large temperature change if the power plant is brought to a complete halt, its temperature then possibly changing from 300" C. down to 60 C.
  • temperature variations of this type only occur every few months during normal power plant operation.
  • the element 8 may be constituted by a tube, and the tubes 7 and 8 can be assembled together merely by inserting the tube 8 into the tube '7. It is of course desirable that the tubes fit together very closely so that a very low resistance to heat conduction will exist between them. To this end, it would be particularly advantageous to construct the assembly of tubes 7 and 8 by inserting a bloom of the material from which the tube 8 is to be made into a hollow bloom of the material from which the tube 7 is to be made, and by simultaneously drawing the two blooms in a suitable drawing, or extrusion, apparatus to give the tubes their final desired dimensions. It is well known that such a technique permits the corrosion-1e sistant tube 3 to be drawn to an extremely small thickness. Moreover, such a drawing operation permits a true metallurgical bond to be created between the two tubes. This bonding can be improved, if desired, by carrying out an intermediate annealing.
  • the element 8 in the form of a coating or layer simply by means of an electrodeposition of nickel or chromium, for example.
  • thermal protective cap 10 Incoloy can be used.
  • a cladding structure for covering a nuclear reactor fuel element which has a tubular configuration and Which is to be disposed in a reactor in which boiling water is present in the region outside the fuel element and a primary coolant vapor to be heated to a predetermined temperature is present in the region enclosed by the fuel element, said cladding structure comprising:
  • An arrangement as defined in claim 1 further comprising a sealing plug disposed at each end of such fuel element for sealing off the fuel element, said plug being made of the same material as said jackets.

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  • Physics & Mathematics (AREA)
  • Engineering & Computer Science (AREA)
  • Plasma & Fusion (AREA)
  • General Engineering & Computer Science (AREA)
  • High Energy & Nuclear Physics (AREA)
  • Preventing Corrosion Or Incrustation Of Metals (AREA)
  • Monitoring And Testing Of Nuclear Reactors (AREA)
US528306A 1965-02-17 1966-02-17 Fuel element heat transfer arrangement Expired - Lifetime US3384551A (en)

Applications Claiming Priority (1)

Application Number Priority Date Filing Date Title
DEL0049979 1965-02-17

Publications (1)

Publication Number Publication Date
US3384551A true US3384551A (en) 1968-05-21

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Family Applications (1)

Application Number Title Priority Date Filing Date
US528306A Expired - Lifetime US3384551A (en) 1965-02-17 1966-02-17 Fuel element heat transfer arrangement

Country Status (3)

Country Link
US (1) US3384551A (de)
DE (1) DE1514115A1 (de)
GB (1) GB1132874A (de)

Cited By (7)

* Cited by examiner, † Cited by third party
Publication number Priority date Publication date Assignee Title
US3669834A (en) * 1968-10-29 1972-06-13 Combustion Eng Core plug for nuclear reactor and method of operating reactor
US3669833A (en) * 1967-09-29 1972-06-13 Belgonucleaire Sa Nuclear fuel
US3850584A (en) * 1970-03-07 1974-11-26 Metallgesellschaft Ag Fuel element can for a nuclear reactor
US3926721A (en) * 1972-06-29 1975-12-16 Atomenergi Ab Method of operating a water-cooled nuclear reactor
DE2626941A1 (de) * 1975-06-26 1977-01-20 Gen Electric Bauteile aus korrosionsbestaendiger zirkoniumlegierung und verfahren zu deren herstellung
US5615238A (en) * 1993-10-01 1997-03-25 The United States Of America As Represented By The United States Department Of Energy Method for fabricating 99 Mo production targets using low enriched uranium, 99 Mo production targets comprising low enriched uranium
US6526115B2 (en) * 2000-07-14 2003-02-25 Kabushiki Kaisha Toshiba Supercritical-pressure water cooled reactor and power generation plant

Citations (4)

* Cited by examiner, † Cited by third party
Publication number Priority date Publication date Assignee Title
US3171789A (en) * 1960-12-09 1965-03-02 Atomic Energy Authority Uk Inhibition of the corrosion of metals by steam at high temperatures
US3212988A (en) * 1961-07-18 1965-10-19 Ringot Claude Fuel element for nuclear reactors
US3291696A (en) * 1962-09-21 1966-12-13 Nihon Genshiryoku Kenkyujo Fuel element for high temperature and high power density nuclear reactor
US3304235A (en) * 1963-12-16 1967-02-14 Snam Spa Nuclear fuel elements formed by metallic uranium or its alloys lined with magnesium or zirconium alloys and process of lining said elements

Patent Citations (4)

* Cited by examiner, † Cited by third party
Publication number Priority date Publication date Assignee Title
US3171789A (en) * 1960-12-09 1965-03-02 Atomic Energy Authority Uk Inhibition of the corrosion of metals by steam at high temperatures
US3212988A (en) * 1961-07-18 1965-10-19 Ringot Claude Fuel element for nuclear reactors
US3291696A (en) * 1962-09-21 1966-12-13 Nihon Genshiryoku Kenkyujo Fuel element for high temperature and high power density nuclear reactor
US3304235A (en) * 1963-12-16 1967-02-14 Snam Spa Nuclear fuel elements formed by metallic uranium or its alloys lined with magnesium or zirconium alloys and process of lining said elements

Cited By (9)

* Cited by examiner, † Cited by third party
Publication number Priority date Publication date Assignee Title
US3669833A (en) * 1967-09-29 1972-06-13 Belgonucleaire Sa Nuclear fuel
US3669834A (en) * 1968-10-29 1972-06-13 Combustion Eng Core plug for nuclear reactor and method of operating reactor
US3850584A (en) * 1970-03-07 1974-11-26 Metallgesellschaft Ag Fuel element can for a nuclear reactor
US3926721A (en) * 1972-06-29 1975-12-16 Atomenergi Ab Method of operating a water-cooled nuclear reactor
DE2626941A1 (de) * 1975-06-26 1977-01-20 Gen Electric Bauteile aus korrosionsbestaendiger zirkoniumlegierung und verfahren zu deren herstellung
US4268586A (en) * 1975-06-26 1981-05-19 General Electric Company Corrosion resistant zirconium alloy structural components and process
US5615238A (en) * 1993-10-01 1997-03-25 The United States Of America As Represented By The United States Department Of Energy Method for fabricating 99 Mo production targets using low enriched uranium, 99 Mo production targets comprising low enriched uranium
US6160862A (en) * 1993-10-01 2000-12-12 The United States Of America As Represented By The United States Department Of Energy Method for fabricating 99 Mo production targets using low enriched uranium, 99 Mo production targets comprising low enriched uranium
US6526115B2 (en) * 2000-07-14 2003-02-25 Kabushiki Kaisha Toshiba Supercritical-pressure water cooled reactor and power generation plant

Also Published As

Publication number Publication date
GB1132874A (en) 1968-11-06
DE1514115A1 (de) 1969-09-04

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