EP0171773A2 - Récipient de stockage des barres combustibles d'éléments combustibles irradiés de réacteurs nucléaires - Google Patents

Récipient de stockage des barres combustibles d'éléments combustibles irradiés de réacteurs nucléaires Download PDF

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Publication number
EP0171773A2
EP0171773A2 EP85110053A EP85110053A EP0171773A2 EP 0171773 A2 EP0171773 A2 EP 0171773A2 EP 85110053 A EP85110053 A EP 85110053A EP 85110053 A EP85110053 A EP 85110053A EP 0171773 A2 EP0171773 A2 EP 0171773A2
Authority
EP
European Patent Office
Prior art keywords
fuel
fuel rod
storage container
insert basket
liners
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.)
Granted
Application number
EP85110053A
Other languages
German (de)
English (en)
Other versions
EP0171773B1 (fr
EP0171773A3 (en
Inventor
Helfrid Dr. Lahr
Bernd Pontani
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.)
Deutsche Gesellschaft fuer Wiederaufarbeitung von Kernbrennstoffen mbH
Original Assignee
Deutsche Gesellschaft fuer Wiederaufarbeitung von Kernbrennstoffen mbH
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 Deutsche Gesellschaft fuer Wiederaufarbeitung von Kernbrennstoffen mbH filed Critical Deutsche Gesellschaft fuer Wiederaufarbeitung von Kernbrennstoffen mbH
Publication of EP0171773A2 publication Critical patent/EP0171773A2/fr
Publication of EP0171773A3 publication Critical patent/EP0171773A3/de
Application granted granted Critical
Publication of EP0171773B1 publication Critical patent/EP0171773B1/fr
Expired legal-status Critical Current

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Classifications

    • G—PHYSICS
    • G21—NUCLEAR PHYSICS; NUCLEAR ENGINEERING
    • G21F—PROTECTION AGAINST X-RADIATION, GAMMA RADIATION, CORPUSCULAR RADIATION OR PARTICLE BOMBARDMENT; TREATING RADIOACTIVELY CONTAMINATED MATERIAL; DECONTAMINATION ARRANGEMENTS THEREFOR
    • G21F5/00—Transportable or portable shielded containers
    • G21F5/005—Containers for solid radioactive wastes, e.g. for ultimate disposal
    • G21F5/008—Containers for fuel elements
    • G21F5/012—Fuel element racks in the containers

Definitions

  • the invention relates to a storage container referred to in the preamble of claim 1.
  • Shielded transport and storage containers made of spherulitic cast iron or steel are used for the transport and storage of irradiated nuclear reactor fuel elements.
  • the interior of the container can have a round or square cross section.
  • Containers with a circular interior have the advantage that they can be manufactured more easily and offer very good storage space utilization.
  • the irradiated fuel elements are accommodated in special insert baskets in these storage containers.
  • the fuel rods removed from the fuel assemblies are filled in tight packing in cans which geometrically correspond to a fuel assembly (DE-OS 32 22 822).
  • the filled cans are inserted into the receiving shafts of the insert basket which are designed for the fuel elements.
  • a major technical problem in the storage of individual fuel rods in the densest possible packing in a storage container is the temperature control of this storage container. Due to the heat of decay of the radioactive fuel, there is a possibility that the temperature inside the container will increase inadmissibly. The heat dissipation from the inside of the fuel rod pack creates problems. This heat dissipation problem can therefore lead to limitations in the packing density or to a longer previous decay time of the fuel elements before they are introduced into the storage container.
  • the invention has for its object to provide a container of the type described in such a way that good heat dissipation from the storage container is achieved and an inadmissible heat impairment of the fuel rods is prevented.
  • the object is achieved in that the individual sleeves in the insert basket are arranged in a circle, that the cross section of the sleeves is in the form of a segment of a circle, that the sleeves are loaded with hold-down springs on their upper end faces, and that the sleeve segments are limited in radial extension to the center in such a way that an empty square shaft is formed in the middle of the insert basket.
  • the circular segment-shaped design of the respective fuel rod bushing results in a good adaptation to the round storage space cross section.
  • the curved back surfaces of the fuel rod liners fit the circular inner wall of the container and thus ensure good heat transfer between the liners and the storage container.
  • Through the Hold-down springs press the respective fuel rod sleeve against the bottom of the storage container in the direction parallel to the axis, so that good heat transfer is also guaranteed there.
  • the empty square shaft that arises in the middle of the storage space enables the scrap that is produced when the fuel rods are separated, that is to say the spacers and the like, to be introduced in the middle.
  • This structural material of the decomposed fuel has a significantly lower heat capacity than the B race on bars. It is also insensitive to the effects of heat. It can endure heat increases without protection. In contrast, the irradiated fuel rods must not exceed the temperature values prescribed by the approval, otherwise leakages could occur. This would result in the escape of fission gases or other radioactive inventory.
  • An advantageous embodiment of the invention is characterized by the features mentioned in claim 2.
  • the double-walled separating segments each create a cavity between two fuel rod liners arranged side by side. This division of the circular storage space allows fuel rod liners with the same configuration to be used. In this case, one fuel rod can each receive the fuel rods of a fuel assembly in an advantageous manner.
  • the cavities in the separating segments offer the possibility of introducing neutron-absorbing substances or heat-conducting substances. The essence of this embodiment of the invention is seen in the fact that the fuel rod liners can have the same configurations.
  • the invention creates a storage container for receiving individual fuel rods, in which fuel rods can be stored, which have a higher heat output. After the fuel elements have been removed from the reactor storage pool and separated, the fuel rods can therefore be brought directly into the container intended for final storage. Another intermediate storage to decrease the temperature is not necessary.
  • a final storage container 11 made of steel (FIGS. 1 and 2) has a circular storage space 13 for receiving individual fuel rods 15 of some irradiated nuclear reactor fuel elements.
  • the fuel rods 15 are packed tightly in four fuel rod liners 17 in the form of segments of a circle. These bushes 17 are closed after loading.
  • the fuel rod liners 17 are inserted into an insert basket 19 located in the circular storage space 13. Seen in cross section, this insert basket 19 has a centrally arranged square shaft 21, from the corners of which diagonal partition walls 23 strive toward the container inner wall 24 of the storage space 13. As a result, four receiving shafts 25 are formed, in which the fuel rod liners 17 are located.
  • the fuel rod liners 17 are designed in the shape of a segment of a circle. Their rear walls 27 abutting against the inner wall 24 of the container are each arc-shaped. The curvature of the rear walls 27 corresponds to the curvature of the inner container wall 24. The radially extending side surfaces 29 of the liners 17 lie parallel to the partition walls 23. The inwardly closing wall 31, which is designed in the form of a lattice, each fuel rod liner 17 runs parallel to the respective side of the square one Middle shaft 21.
  • the fuel rod liners 17 are at their transition from the radial side surfaces 29 flattened to their arcuate rear wall 27.
  • Each fuel rod can 17 can receive the fuel rods from two disassembled irradiated nuclear reactor fuel elements.
  • the loading is carried out while the fuel rod liner 17 is lying down.
  • the fuel rod liner 17 lies on the rear wall 27.
  • the grid-shaped wall 31 has not yet been inserted. About this open area B are racing rods loaded into the fuel rod bushing 17th
  • the wall 31 is welded in after loading.
  • a stepped cover 33 (Fig. 1) which is screwed ELA deö réelle including a seal not shown with bolts 35 to a corresponding projection 37 of the B.
  • a further closure cover 41 is arranged above this screwed cover 33, which is inserted into the loading opening and welded to the container wall 43.
  • the repository container 11 is placed in a shield transport container 45 in the illustration shown (FIGS. 1 and 2).
  • the loading opening of the shielding transport container 45 is secured by a screwed-on closure cap 47.
  • a polyethylene layer 49 is used in the inner wall of the shielding transport container 45 for neutron shielding.
  • the shielding transport container 45 is provided with supporting pins 51 fastened to the outer circumference.
  • the filled fuel rod liners 17 each have a handling block 55 on their upper end faces 53, to which suitable lifting devices can engage.
  • the top End faces 53 of the fuel rod liners 17 are acted upon by hold-down springs 57 which are supported on the screwed-on cover 33.
  • the individual fuel rods 15 are introduced into the segment-shaped fuel rod liners 17. After loading, the fuel rod liners 17 are closed. The fuel rod liners 17 are grasped via the handling block 55 and inserted into a receiving shaft 25 of the insert basket 19. Hold-down springs 57 are placed on the upper end face 53 of the fuel rod liners 17, which press against the fuel rod liners 17 when the first sealing cap 33 is screwed on and thereby cause the fuel rod liners 17 to bear against the bottom of the container. The fuel rod liners 17 rest with their arc-shaped rear walls 27 on the inner wall 24 of the container. Good heat transfer to the container body is guaranteed.
  • the empty square central shaft 21 is filled with fuel element structural parts 63 which were separated when the fuel elements were disassembled. These are the head and foot pieces as well as the spacers with the control rod guide tubes. The fuel assembly structural parts are compacted.
  • FIG. 3 shows the cross section of a circular storage space 71 of a final storage container 73 of a modified embodiment.
  • a modified insert basket 75 is used, which in the middle of the Storage room 71 also has a square central shaft 77.
  • This square central shaft 77 is held by partitions 78, 79 which extend from the corners and which are supported radially against the inner wall 81 of the container.
  • the partitions 78 and 79 of each pair are connected to one another by an arcuate rear wall 83.
  • a pair of dividing walls 87, 89 likewise runs from the center of the side surfaces 85 of the square central shaft 77 to the container inner wall 81, the dividing walls 87 and 89 of which are each connected at their ends by a short rear wall 91.
  • the rear walls 83 and 91 of the pairs of dividing walls 78, 79 and 87, 89 facing the inner wall 81 of the container are formed in an arc shape.
  • a fuel rod sleeve 93 in the form of a segment of a circle.
  • These fuel rod liners 93 each have an arcuate rear wall 95.
  • the radial side surfaces 97 of the fuel rod liners 95 run parallel to the respectively adjacent partitions of the partition wall pairs 78, 79 and 87, 89.
  • the inner end surface 99 of the fuel rod liners 93 is slightly curved.
  • each fuel rod liner 93 can accommodate the fuel rods 101 of an individual fuel assembly.
  • the fuel rod liners of this embodiment are loaded on the end face.
  • the cross section of the fuel rod liners 93 is desirably always of the same design in order for the method for the front loading of the fuel rod liners 93 not too complicated and without being able to carry out modifications. After loading, the upper end wall is welded onto the respective fuel rod sleeve 93.
  • a suction pipe 103 is provided in the circular storage space 81 in order to be able to remove the water from the container 73 after loading.
  • inclined guide webs 105 are attached in the upper region. These upper guide webs 105 interact with inclined run-up surfaces 106, which are introduced into the respectively adjacent partition wall of a pair of partition walls 78 ', 79' or 87 ', 89' of the insert basket 75 '.
  • inclined guide surfaces 109 are attached at the lower end of the insert basket 75 'in the vicinity of the bottom of the storage container 73'. The guide webs 105 and the guide surfaces 109 are intended to press the fuel rod liners 93 'against the inner wall 81' of the container when they are inserted.

Landscapes

  • Physics & Mathematics (AREA)
  • Engineering & Computer Science (AREA)
  • General Engineering & Computer Science (AREA)
  • High Energy & Nuclear Physics (AREA)
  • Monitoring And Testing Of Nuclear Reactors (AREA)
EP85110053A 1984-08-17 1985-08-09 Récipient de stockage des barres combustibles d'éléments combustibles irradiés de réacteurs nucléaires Expired EP0171773B1 (fr)

Applications Claiming Priority (2)

Application Number Priority Date Filing Date Title
DE3430243A DE3430243C2 (de) 1984-08-17 1984-08-17 Lagerbehälter zur Aufnahme von vereinzelten Brennstäben bestrahlter Kernreaktorbrennelemente
DE3430243 1984-08-17

Publications (3)

Publication Number Publication Date
EP0171773A2 true EP0171773A2 (fr) 1986-02-19
EP0171773A3 EP0171773A3 (en) 1987-04-15
EP0171773B1 EP0171773B1 (fr) 1989-11-15

Family

ID=6243246

Family Applications (1)

Application Number Title Priority Date Filing Date
EP85110053A Expired EP0171773B1 (fr) 1984-08-17 1985-08-09 Récipient de stockage des barres combustibles d'éléments combustibles irradiés de réacteurs nucléaires

Country Status (4)

Country Link
US (1) US4680159A (fr)
EP (1) EP0171773B1 (fr)
CA (1) CA1234433A (fr)
DE (2) DE3430243C2 (fr)

Cited By (5)

* Cited by examiner, † Cited by third party
Publication number Priority date Publication date Assignee Title
US4908515A (en) * 1985-12-27 1990-03-13 Nus Corporation Method of efficiently storing spent nuclear fuel rods in a cylindrical container
DE3933530A1 (de) * 1989-10-07 1991-04-18 Wiederaufarbeitung Von Kernbre Lagerbuechse zur aufnahme von einzelnen brennstaeben bestrahlter kernreaktorbrennelemente
WO1997029489A1 (fr) * 1996-02-06 1997-08-14 British Nuclear Fuels Plc Conteneur etanche pour assemblages combustibles de reacteurs a eau pressurisee
EP1103984A1 (fr) * 1999-06-19 2001-05-30 GNB Gesellschaft für Nuklear-Behälter mbH Conteneur de transport et/ou de stockage d'objets radioactifs dégageant de la chaleur
EP1122745A1 (fr) * 1999-12-15 2001-08-08 GNB Gesellschaft für Nuklear-Behälter mbH Conteneur pour le transport et/ou le stockage de matières radioactives dégageant de la chaleur et procédé de fabrication d'un tel conteneur

Families Citing this family (17)

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Publication number Priority date Publication date Assignee Title
US4780269A (en) * 1985-03-12 1988-10-25 Nutech, Inc. Horizontal modular dry irradiated fuel storage system
DE3620737C1 (de) * 1986-06-20 1987-10-01 Wiederaufarbeitung Von Kernbre Doppelbehaeltersystem zum Transport und zur Lagerung von radioaktiven Stoffen
DE3802966A1 (de) * 1987-10-02 1989-04-20 Wiederaufarbeitung Von Kernbre Verfahren und vorrichtung zur behandlung eines von brennstaeben befreiten brennelementskelettes eines bestrahlten kernreaktorbrennelementes
US4926046A (en) * 1988-12-12 1990-05-15 Westinghouse Electric Corp. Volumetrically efficient container apparatus
US5180540A (en) * 1991-03-25 1993-01-19 B&W Fuel Company Fuel rod consolidation structure
FR2709116B1 (fr) * 1993-08-20 1995-10-27 Cogema Dispositif de stockage d'objets cylindriques, à chargement et déchargement rapides.
JP3516978B2 (ja) * 1994-04-15 2004-04-05 株式会社東芝 燃料集合体輸送容器
US5615240A (en) * 1994-10-27 1997-03-25 General Electric Company Nuclear fuel bundle packaging apparatus
US20010011711A1 (en) 1996-05-03 2001-08-09 Graham Nicholson Container for nuclear fuel transportation
GB9609304D0 (en) * 1996-05-03 1996-07-10 British Nuclear Fuels Plc Improvements in and relating to fuel transportation
FR2758646B1 (fr) * 1997-01-21 2000-07-13 Toshiba Kk Recipient et procede de transport d'ensembles de combustible nucleaire
BE1011646A3 (fr) * 1997-03-05 1999-11-09 Toshiba Kk Appareils et procede de protection et de transport d'ensembles combustibles nucleaires.
ATE327559T1 (de) * 2001-10-23 2006-06-15 Nuklear Service Gmbh Gns Tragzapfen für zur aufnahme radioaktiver stoffe bestimmte behälter
CA2858381C (fr) 2011-12-08 2020-03-24 Atomic Energy Of Canada Limited/Energie Atomique Du Canada Limitee Appareil pour maintenir des objets radioactifs
US9831006B2 (en) 2013-02-13 2017-11-28 Bwxt Mpower, Inc. Shipping container for unirradiated nuclear fuel assemblies
JP6759037B2 (ja) * 2016-09-30 2020-09-23 三菱重工業株式会社 使用済燃料集合体の収納方法及び収納容器
TWI795484B (zh) 2017-12-20 2023-03-11 美商Ｔｎ美國有限責任公司 用於燃料總成的模組提籃總成

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FR1290757A (fr) * 1960-06-08 1962-04-13 Atomic Energy Commission Container de transport pour matière radio-active
DE2735924A1 (de) * 1976-08-25 1978-03-02 Atomic Energy Authority Uk Aufbau fuer transport und lagerung von radioaktiven kernbrennstoffelementen
FR2424610A1 (fr) * 1978-04-28 1979-11-23 Lemer & Cie Dispositif interne demontable permettant d'homogeneiser la temperature de produits radioactifs dans un conteneur
GB2055671A (en) * 1979-07-18 1981-03-11 British Nuclear Fuels Ltd Transport and storage of irradiated nuclear fuel elements
DE3222822A1 (de) * 1982-06-18 1983-12-29 GNS Gesellschaft für Nuklear-Service mbH, 4300 Essen Anordnung fuer den transport und fuer die lagerung von brennstaeben bestrahlter brennelemente

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Publication number Priority date Publication date Assignee Title
FR1290757A (fr) * 1960-06-08 1962-04-13 Atomic Energy Commission Container de transport pour matière radio-active
DE2735924A1 (de) * 1976-08-25 1978-03-02 Atomic Energy Authority Uk Aufbau fuer transport und lagerung von radioaktiven kernbrennstoffelementen
FR2424610A1 (fr) * 1978-04-28 1979-11-23 Lemer & Cie Dispositif interne demontable permettant d'homogeneiser la temperature de produits radioactifs dans un conteneur
GB2055671A (en) * 1979-07-18 1981-03-11 British Nuclear Fuels Ltd Transport and storage of irradiated nuclear fuel elements
DE3222822A1 (de) * 1982-06-18 1983-12-29 GNS Gesellschaft für Nuklear-Service mbH, 4300 Essen Anordnung fuer den transport und fuer die lagerung von brennstaeben bestrahlter brennelemente

Cited By (5)

* Cited by examiner, † Cited by third party
Publication number Priority date Publication date Assignee Title
US4908515A (en) * 1985-12-27 1990-03-13 Nus Corporation Method of efficiently storing spent nuclear fuel rods in a cylindrical container
DE3933530A1 (de) * 1989-10-07 1991-04-18 Wiederaufarbeitung Von Kernbre Lagerbuechse zur aufnahme von einzelnen brennstaeben bestrahlter kernreaktorbrennelemente
WO1997029489A1 (fr) * 1996-02-06 1997-08-14 British Nuclear Fuels Plc Conteneur etanche pour assemblages combustibles de reacteurs a eau pressurisee
EP1103984A1 (fr) * 1999-06-19 2001-05-30 GNB Gesellschaft für Nuklear-Behälter mbH Conteneur de transport et/ou de stockage d'objets radioactifs dégageant de la chaleur
EP1122745A1 (fr) * 1999-12-15 2001-08-08 GNB Gesellschaft für Nuklear-Behälter mbH Conteneur pour le transport et/ou le stockage de matières radioactives dégageant de la chaleur et procédé de fabrication d'un tel conteneur

Also Published As

Publication number Publication date
US4680159A (en) 1987-07-14
DE3430243A1 (de) 1986-02-27
DE3574306D1 (en) 1989-12-21
DE3430243C2 (de) 1986-11-27
EP0171773B1 (fr) 1989-11-15
CA1234433A (fr) 1988-03-22
EP0171773A3 (en) 1987-04-15

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