US3735550A - Loading of fuel rods - Google Patents

Loading of fuel rods Download PDF

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Publication number
US3735550A
US3735550A US00105392A US3735550DA US3735550A US 3735550 A US3735550 A US 3735550A US 00105392 A US00105392 A US 00105392A US 3735550D A US3735550D A US 3735550DA US 3735550 A US3735550 A US 3735550A
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US
United States
Prior art keywords
trough
pellets
fuel rod
shaped
path
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
US00105392A
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English (en)
Inventor
C Moore
W Heer
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.)
Babcock and Wilcox Co
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Babcock and Wilcox Co
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 by Babcock and Wilcox Co filed Critical Babcock and Wilcox Co
Application granted granted Critical
Publication of US3735550A publication Critical patent/US3735550A/en
Anticipated expiration legal-status Critical
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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
    • G21C21/08—Manufacture of fuel elements or breeder elements contained in non-active casings by a slip-fit cladding process by crimping the jacket around the fuel
    • 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

  • ABSTRACT A method of loading fuel rods of the nuclear variety with radioactive pellets wherein the rod is evacuated, subsequently filled with an inert gaseous atmosphere, loaded with such pellets in linear array, and sealed.
  • the pellets in this method are brought in linear array from a supply station to a predetermined situs and then are transferred in such array into a linear bed which is subsequently sealed, evacuated of atmosphere and then filled with helium.
  • the pellets are then transferred in such linear array from the bed to a communicating fuel rod and the latter is sealed in form for use in the core of a nuclear reactor.
  • This invention relates to the processing of fuel rods of a nuclear nature.
  • this invention relates to the loading of fuel rods with pellets of the nuclear variety in an inert atmosphere and includes a device for accomplishing the same.
  • the subject invention answers the needs of the art with special emphasis on the effective loading of such fuel rods in an efficient manner with optimum results in the shortest possible time including the avoidance of atmospheric contamination during such loading.
  • Another object is to provide a method of loading such fuel rods in an efiective and efficient manner for the attainment of optimum results in the shortest possible time.
  • a further object is a method of loading such fuel rods with assurance that the interior of such rod has the proper atmosphere.
  • a further object is the provision of a method wherein the pellets are assured of the proper environment within such fuel rod after loading for efficient and effective utility in the core of a nuclear reactor.
  • FIG. I is a top plan view of the device of this invention.
  • FIG. 2 is a side view of the device of FIG. 1.
  • FIG. 3 is a view taken on line 3-3 of FIG. 1 showing a cross-section of the empty bed in the closed position.
  • FIG. 4 is a view taken on line 4-4 of FIG. 3 showing the means for sealing the fuel rod operatively to the bed.
  • FIG. 5 is a view taken on line 5-5 of FIG. 3 showing the sealing overlay of the device.
  • FIG. 6 is a view taken on line 6-6 of FIG. 1 showing the bed in the open position for the reception of the radioactive pellets from the linear conveyor.
  • FIG. 7 is a view taken on line 6-6 of FIG. 1 showing the pellets in position in the sealed bed.
  • FIG. 8 is a side view showing a pivoting device for use with the tilting conveyor of FIGS. 6 and 7.
  • FIG. 9 is a side view of a device for use in applying a sealed overlay to the bed of the device of this invention.
  • FIG. 10 is a side view in section showing an apparatus for use in controlling the atmosphere during the sealin of the loaded fuel rod.
  • the method of this invention encompasses loading fuel rods with a plurality of pellets of a radioactive varietyby the transportation of such pellets in linear array along a movable longitudinal path from a supply station to a situs adjacent an open longitudinal bed and the transference of such pellets transversely into such bed, which is in the form of a V-shaped longitudinal trough, accompanied by the sealing of such bed or trough.
  • the voids of the trough are then evacuated and subsequently refilled with an inert gaseous medium, at which time, the pellets are transferred from such longitudinal trough into such fuel rod by means of a ram and the fuel rod is sealed with a closure.
  • the device for use in this invention includes a bed in the form of a long trough 10 having. a V-shaped channel provided at one end with sealing means for separable engagement to the open end of a fuel rod 12 of the nuclear variety.
  • the trough 10 is also provided with a lid or cover in the form of a sealing overlay 13 which is pivotally mounted by conventional means 14 in spaced relationship along the length of the trough It) for separable engagement with the upper surface 15 thereof.
  • the sealing means 11 of the trough as shown in FIGS.
  • 3 and 4 is in the form of a receptive slot having an open end which fits snugly around the outer periphery or surface of the open end portion of a fuel rod 12 when such rod 12 is inserted into such sealing means.
  • the other end of the receptive slot communicates with the V-shaped channel of trough 10.
  • a vacuum source 16 communicates with the lid or sealing overlay 13 through a trunk line 17 which is provided with access lines 18.
  • the latter lines are opera fively connected in spaced relationship along the length of the lid 13 and communicates with a series of inter.- connected channels 19 as shown in FIG. 5 for the evacuation of the trough 10 which communicates with fuel rod 12 as depicted in FIG. 1.
  • a source of an inert gaseous medium such as helium 21 is operatively connected to trunk line 17 for back-fill operations prior to transference of the pellets to the fuel rod 12.
  • the end of the trough 10 adjacent the supply station is provided with a ram 20 which is driven by motive means 24.
  • the latter ram 20 is insertable sealed in the V-shaped channel of the trough l and functions to push the pellets of nuclear fuel along the length of the trough towards and into the open end of the fuel rod 12.
  • the ram is a nylon line of the cord-type variety.
  • a movable longitudinal path or U-shaped conveyor 23 extends from a supply station 22 to a coextensive position adjacent one side of the longitudinal V-shaped trough l0 opposite the side on which the sealing overlay 13 is positioned.
  • the longitudinal path or conveyor 23 is pivotally mounted by conventional pivot means 24 in spaced relationship along the longitudinal side of the trough 10.
  • the conveyor 23 is provided with retention means 24 in the form of a guard rail and guide means 25 in the form of an elongated arm which substantially extends the length of the conveyor 23.
  • the latter two means 24 and 25 both serve to maintain the radioactive pellets 26 in linear array as they are moved on the conveyor 23.
  • the pellets 26 are received from a supply station 22 in linear array and are moved longitudinally along the conveyor 23.
  • the conveyor is pivotally tilted as shown in FIG. 6 and the pellets are deposited in the V-shaped channel of the trough by guide means 25.
  • the conveyor is then returned to the original position as shown in FIG.
  • the pivotal movement of the conveyor 23 may be accomplished by means of a device such as that shown in FIG. 8 while the overlay seal 13 may be applied to the upper surface of the V-shaped trough by means of a device as shown in FIG. 9.
  • the open end of the fuel rod 12 is inserted through a sealing device 31 of the ball valve variety and into a chamber 32 having a controlled environment relative to atmosphere.
  • the latter chamber is provided with access holes (not shown) of a sealed nature for the manual part of the procedure.
  • the end of the rod in the chamber is then manually pushed through a second sealing device 33 also of the ball valve variety and a transition block 34 into separable engagement with the sealing means 11 of the V-shaped trough as shown in FIGS. 1 and 10.
  • the method consists in the receiving of the radioactive pellets 26 from a supply station or source 22 by the relatively long conveyor 23 which transports or moves the pellets 26 in a straight line to a predetermined position along an adjacent side of the V-shaped trough 10.
  • the conveyor 23 is then pivoted and the pellets are transversely transferred into such trough 10 without damage and the cover or lid 13 in the form of an overlay is placed in position over the trough l0 and sealed.
  • the voids in the trough 10, especially those around the pellets 26 are then evacuated of atmosphere and subsequently refilled with an inert gaseous medium such as helium.
  • the pellets 26 are transferred along such trough under the atmosphere of helium into the open end of the fuel rod 12 by means of a pushing action on the part of the ram 20. It should be noted that the fuel rod 12 was initially sealed in communicating relationship to the trough l0 and the void therein was also evacuated simultaneously with those of the trough l0.
  • the fuel rod 12 is separated from engagement with the trough l0 and withdrawn through the transition block 34 and sealing device 33 into the chamber 32 where a closure is fitted to the end thereof and the fully withdrawn fuel rod is then ready for use in the core of a nuclear reactor.
  • a process of loading fuel rods with pellets of a radioactive variety comprising:
  • a device for use in loading fuel rods with pellets of a radioactive variety comprising:
  • a V-shaped longitudinal trough mounted on said base and adapted to receive said pellets in linear array
  • said trough having one end adapted to axially receive an open end of said fuel rod
  • a movable longitudinal path of the U-shaped variety pivotally mounted in longitudinal relationship along one side of said V-shaped trough
  • a sealing overlay pivotally mounted along the other side of said V-shaped trough for separable overhead engagement with said trough
  • said overlay provided with means for providing in sequence a vacuum and inert gaseous medium to said trough, and
  • Transfer means adapted for longitudinal movement of said pellets along said V-shaped trough into said fuel rod.
  • sealing means is a receptive slot for snugly fitting around the outer peripheral end portion of a fuel rod.

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  • Engineering & Computer Science (AREA)
  • Physics & Mathematics (AREA)
  • Manufacturing & Machinery (AREA)
  • Plasma & Fusion (AREA)
  • General Engineering & Computer Science (AREA)
  • High Energy & Nuclear Physics (AREA)
  • Monitoring And Testing Of Nuclear Reactors (AREA)
US00105392A 1971-01-11 1971-01-11 Loading of fuel rods Expired - Lifetime US3735550A (en)

Applications Claiming Priority (1)

Application Number Priority Date Filing Date Title
US10539271A 1971-01-11 1971-01-11

Publications (1)

Publication Number Publication Date
US3735550A true US3735550A (en) 1973-05-29

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ID=22305585

Family Applications (1)

Application Number Title Priority Date Filing Date
US00105392A Expired - Lifetime US3735550A (en) 1971-01-11 1971-01-11 Loading of fuel rods

Country Status (11)

Country Link
US (1) US3735550A (enrdf_load_stackoverflow)
JP (1) JPS5122594B1 (enrdf_load_stackoverflow)
BE (1) BE777699A (enrdf_load_stackoverflow)
CA (1) CA956090A (enrdf_load_stackoverflow)
CH (1) CH554058A (enrdf_load_stackoverflow)
DE (1) DE2162698C3 (enrdf_load_stackoverflow)
ES (2) ES398714A1 (enrdf_load_stackoverflow)
FR (1) FR2121687B1 (enrdf_load_stackoverflow)
IT (1) IT949322B (enrdf_load_stackoverflow)
LU (1) LU64577A1 (enrdf_load_stackoverflow)
NL (1) NL173326C (enrdf_load_stackoverflow)

Cited By (11)

* Cited by examiner, † Cited by third party
Publication number Priority date Publication date Assignee Title
US3841467A (en) * 1972-06-20 1974-10-15 Univ Missouri Product and process for making improved strength dental amalgam
US3907123A (en) * 1973-05-31 1975-09-23 Exxon Nuclear Co Inc Fuel rod pellet loading head
US3925965A (en) * 1973-01-22 1975-12-16 Exxon Nuclear Co Inc Fuel rod pellet loading assembly
US4235066A (en) * 1978-05-30 1980-11-25 General Electric Company Nuclear fuel rod loading apparatus
US4292788A (en) * 1980-02-11 1981-10-06 General Electric Company Nuclear fuel rod loading apparatus
US4558982A (en) * 1984-06-27 1985-12-17 The United States Of America As Represented By The Secretary Of The United States Department Of Energy Evacuate and backfill apparatus and method
US4980119A (en) * 1989-04-04 1990-12-25 General Electric Company Multizone automated nuclear fuel rod loading system
US5251244A (en) * 1992-08-21 1993-10-05 General Electric Company Nuclear fuel pellet loading system
WO2004059658A1 (fr) * 2002-12-24 2004-07-15 Belgonucleaire Sa Methode et dispositif de chargement de pastilles de combustible nucleaire
US20060146974A1 (en) * 2005-01-06 2006-07-06 Crawford Michael L Segment make-up system and method for manufacturing nuclear fuel rods
US20060285626A1 (en) * 2005-05-17 2006-12-21 Bailey William E Nuclear fuel rod loading method and apparatus

Families Citing this family (4)

* Cited by examiner, † Cited by third party
Publication number Priority date Publication date Assignee Title
JPS58172427U (ja) * 1982-05-14 1983-11-17 前田　満枝 装飾用鉢植え
FR2577065B1 (fr) * 1985-02-07 1987-03-06 Commissariat Energie Atomique Dispositif d'engainage de pastilles combustibles
US4748798A (en) * 1985-05-10 1988-06-07 Japan Nuclear Fuel Co., Ltd. Apparatus for automatically loading nuclear fuel pellets
DE4125935A1 (de) * 1991-08-05 1993-02-11 Siemens Ag Verfahren und vorrichtung zum foerdern von pulver von einer abgabestation zu einer auffangstation

Citations (2)

* Cited by examiner, † Cited by third party
Publication number Priority date Publication date Assignee Title
US3212226A (en) * 1961-05-31 1965-10-19 Westinghouse Electric Corp Method and apparatus for loading members
US3364958A (en) * 1965-06-28 1968-01-23 Calumet & Hecla Method of and structure for pressurizing tube sections

Patent Citations (2)

* Cited by examiner, † Cited by third party
Publication number Priority date Publication date Assignee Title
US3212226A (en) * 1961-05-31 1965-10-19 Westinghouse Electric Corp Method and apparatus for loading members
US3364958A (en) * 1965-06-28 1968-01-23 Calumet & Hecla Method of and structure for pressurizing tube sections

Cited By (15)

* Cited by examiner, † Cited by third party
Publication number Priority date Publication date Assignee Title
US3841467A (en) * 1972-06-20 1974-10-15 Univ Missouri Product and process for making improved strength dental amalgam
US3925965A (en) * 1973-01-22 1975-12-16 Exxon Nuclear Co Inc Fuel rod pellet loading assembly
US3907123A (en) * 1973-05-31 1975-09-23 Exxon Nuclear Co Inc Fuel rod pellet loading head
US4235066A (en) * 1978-05-30 1980-11-25 General Electric Company Nuclear fuel rod loading apparatus
US4292788A (en) * 1980-02-11 1981-10-06 General Electric Company Nuclear fuel rod loading apparatus
US4558982A (en) * 1984-06-27 1985-12-17 The United States Of America As Represented By The Secretary Of The United States Department Of Energy Evacuate and backfill apparatus and method
US4980119A (en) * 1989-04-04 1990-12-25 General Electric Company Multizone automated nuclear fuel rod loading system
US5251244A (en) * 1992-08-21 1993-10-05 General Electric Company Nuclear fuel pellet loading system
WO2004059658A1 (fr) * 2002-12-24 2004-07-15 Belgonucleaire Sa Methode et dispositif de chargement de pastilles de combustible nucleaire
US20060188053A1 (en) * 2002-12-24 2006-08-24 Alain Vandergheynst Method and device for loading nuclear fuel pellets
US20060146974A1 (en) * 2005-01-06 2006-07-06 Crawford Michael L Segment make-up system and method for manufacturing nuclear fuel rods
US7593501B2 (en) 2005-01-06 2009-09-22 Areva Np Inc. Segment make-up system and method for manufacturing nuclear fuel rods
US20060285626A1 (en) * 2005-05-17 2006-12-21 Bailey William E Nuclear fuel rod loading method and apparatus
WO2006125080A3 (en) * 2005-05-17 2007-11-22 Areva Np Inc Nuclear fuel rod laoding method and apparatus
US7539280B2 (en) * 2005-05-17 2009-05-26 Areva Np Inc. Nuclear fuel rod loading method and apparatus

Also Published As

Publication number Publication date
IT949322B (it) 1973-06-11
DE2162698A1 (de) 1972-08-10
NL7200380A (enrdf_load_stackoverflow) 1972-07-13
FR2121687B1 (enrdf_load_stackoverflow) 1975-10-24
CH554058A (fr) 1974-09-13
NL173326B (nl) 1983-08-01
NL173326C (nl) 1984-01-02
CA956090A (en) 1974-10-15
JPS5122594B1 (enrdf_load_stackoverflow) 1976-07-10
DE2162698B2 (de) 1974-10-17
FR2121687A1 (enrdf_load_stackoverflow) 1972-08-25
ES433477A1 (es) 1976-11-16
LU64577A1 (enrdf_load_stackoverflow) 1972-06-22
ES398714A1 (es) 1976-01-01
BE777699A (fr) 1972-07-05
DE2162698C3 (de) 1975-06-12

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