EP0250902A2 - Système à récipients doubles pour le transport et le stockage de matériaux radioactifs - Google Patents

Système à récipients doubles pour le transport et le stockage de matériaux radioactifs Download PDF

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Publication number
EP0250902A2
EP0250902A2 EP87107997A EP87107997A EP0250902A2 EP 0250902 A2 EP0250902 A2 EP 0250902A2 EP 87107997 A EP87107997 A EP 87107997A EP 87107997 A EP87107997 A EP 87107997A EP 0250902 A2 EP0250902 A2 EP 0250902A2
Authority
EP
European Patent Office
Prior art keywords
polyethylene
rings
container
shielding
container system
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.)
Withdrawn
Application number
EP87107997A
Other languages
German (de)
English (en)
Other versions
EP0250902A3 (fr
Inventor
Franz-Wolfgang Popp
Bernd Pontani
Erich Ernst
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 EP0250902A2 publication Critical patent/EP0250902A2/fr
Publication of EP0250902A3 publication Critical patent/EP0250902A3/fr
Withdrawn legal-status Critical Current

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    • 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
    • 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
    • G21F1/00—Shielding characterised by the composition of the materials
    • G21F1/02—Selection of uniform shielding materials
    • G21F1/10—Organic substances; Dispersions in organic carriers
    • 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

Definitions

  • the invention relates to a double container system according to the preamble of claim 1.
  • neutron shielding layer made of a hydrogen-containing material, preferably polyethylene, for additional shielding of the neutron radiation emerging from the radioactive nuclear fuel around the storage container. Because of the poor thermal conductivity of such neutron shielding materials, it is known to arrange thermally conductive webs in this layer, which thermally conductively connect the container surface to the outside atmosphere.
  • a shielding container is known from DE-OS 2831646, which has a neutron shielding layer made of granular polyethylene and whose heat conducting webs are connected to an outer surface of a relatively thin-walled steel jacket for better dissipation of the decay heat to the outside world.
  • This thin steel jacket only serves to dissipate the heat of decay to the outside world.
  • the shielding container In double-container systems in which the two containers arranged one inside the other have to meet different requirements, the shielding container usually has a wall thickness of approximately 200 mm in order to ensure the necessary shielding against radioactive radiation.
  • this thick-walled outer Shielding containers provide mechanical protection for the internal container during transport and shock loads.
  • the inner storage container holds the radioactive substances in a gas-tight manner and is therefore provided with a double-lid system, the outer secondary lid of which is welded gas-tight to the container body.
  • the object of the invention is to create a neutron moderator structure for a double container system of the type described at the outset, which nevertheless allows good heat dissipation with good shielding over its entire lateral surface.
  • the moderator structure according to the invention is interrupted to produce the thermal bridges in its outer surface only by the horizontal webs of the H-profile rings.
  • the arrangement of the lateral legs perpendicular to the web fix the polyethylene rings and at the same time ensure good heat conduction over their sufficiently large areas which are in metallic contact with the inner surface of the shielding container or the outer surface of the inner storage container.
  • the thickness and spacing of the horizontal webs can be selected according to the heat to be dissipated.
  • the invention makes it possible to carry out the moderator structure in a technically simple manner, since the polyethylene rings can be stacked on top of one another in a simple manner while being fixed by the H-profile rings. This stacking creates a cylindrical bond.
  • An advantageous embodiment of the invention is characterized by the features mentioned in claim 2. This configuration ensures that the individual segments are covered at room temperature.
  • a further advantageous embodiment of the invention is characterized by the features of claim 3.
  • a good installation possibility of these rings is achieved by the joints of the H-profile rings. These rings can be inserted under a prestress, so that the outer limbs of the profiled ring lie closely against the inner surface of the shielding container.
  • the polyethylene rings are made of ultra-high-molecular low-pressure polyethylene. It has surprisingly been found that this ultra-high molecular weight, low-pressure polyethylene is particularly suitable for shielding a double-container package. This is attributed to the fact that this low-pressure polyethylene has no plasticizers and solvents and thus suffers minimal outgassing. In addition, there is no melting of the low-pressure polyethylene in the temperature ranges used. In addition, the low-pressure polyethylene remains rubber-elastic up to 250 degrees Celsius.
  • the neutron moderator structure is spring-loaded on its upper side. This spring load acting in the longitudinal direction enables length compensation of the moderator structure due to the heat development.
  • the features of claim 7 advantageously ensure that the neutron moderator structure is kept free of shock loads.
  • the inner storage container will remove impact loads via the guides on the shielding container.
  • the double container package shown has a shielding container 11 made of GGG 40, the loading opening 13 of which is closed by a screwed-in shielding cover 15.
  • a storage container 17 made of steel is used, which has an insert grille 19 in its cavity for receiving individual, densely arranged fuel rods 21 of a disassembled nuclear reactor fuel element.
  • the scrap parts 25 of the disassembled nuclear reactor fuel elements are introduced while being filled with a setting compound, such as synthetic resin.
  • the storage space of the storage container 17 is closed by a screwed-on primary cover 27, including sealing rings 29 and 31.
  • a secondary cover 33 which is flush with the upper outer edge of the storage container 17 is inserted in the loading opening of the storage container 17 and is welded to the container body.
  • the shielding cover 15 of the shielding container 11 has an inner cylindrical recess 35, into which the upper end of the storage container 17 protrudes.
  • the lower part of the storage container 17 is guided by an inner extension 37 of the shielding container 11.
  • the inner diameter of the shielding container 11 opens over this inner shoulder 37 and thus results in an annular gap 39 in which a neutron moderator structure 41 is arranged.
  • This neutron moderator 41 consists of individual superimposed polyethylene rings 43.
  • an H-shaped aluminum ring 45 (FIG. 2) is arranged between two polyethylene rings 43 one above the other. This stack-like arrangement creates a cylindrical composite of the moderator structure 41.
  • the horizontal web 47 of each individual profile ring 45 breaks through the neutron moderator layer 41 only on a small area.
  • the vertical legs 49 lie adjacent to the inner surface of the shielding container 11 or to the outer surface of the storage container 17.
  • the polyethylene rings 43 each consist of individual composite segments 51, the joints 53 of which are at an acute angle ⁇ to the center line (FIG. 3).
  • the H-profile rings 45 made of aluminum are each interrupted by a parting line 55, so that there is the possibility of introducing the H-profile rings 45 into the double container container with a prestress. A close fit of the outer legs 49 of the profile rings 45 on the inner surface of the shielding container 11 was achieved.
  • the double container is assembled in the following way:
  • the moderator structure 41 is inserted into the open shielding container 11 by introducing the individual layers of polyethylene rings 43 and intermediate H-profile rings 45 brought in.
  • the length of the cylindrical moderator structure 41 extends into the lid area or into the bottom area of the storage container 17 which is subsequently introduced. Sufficient shielding is thus ensured over the height of the storage container 17.
  • the storage container 17 is loaded with the radioactive substances in a hot cell.
  • the primary cover 27 is inserted and screwed onto the projecting wall of the storage container 17.
  • the primary cover 33 can then be welded.
  • the storage container 17 is then introduced into the shielding container 11.
  • the shielding cover 15 is screwed into the opening of the shielding container 11.
  • the storage container 17 is now fixed. Any shock loads during transport are absorbed by the guide 35 in the shielding cover 15 or the guide 37 in the bottom region of the shielding container.
  • the neutron moderator 41 is kept free of shock loads.
  • the parting lines 53 of the polyethylene rings 43 are arranged by their bevel ⁇ such that the individual segments 51 already overlap at room temperature. At the highest expected operating temperature, the parting lines 53 are closed.
  • FIG. 5 shows a compression spring arrangement 57 which is supported between the surface of the moderator structure 41 and the shielding cover 15 of the shielding container 11.
  • On the horizontal web 47 of the uppermost H-profile-shaped aluminum ring 45 is a flat one Ring 59 put on.
  • this ring 59 twelve leaf spring segments 61 are fastened with a rivet 63.
  • Each leaf spring segment 61 has two upwardly bent spring legs 65 and 67, the free ends of which bear against the shielding cover 15.
  • the moderator structure 41 When the double container bundle is heated, the moderator structure 41 can expand upwards in its longitudinal direction.
  • the spring travel serves as heat compensation and fixation of the moderator structure 41 even at room temperature. It makes sense to select the spring force according to the moderator weight.

Landscapes

  • Physics & Mathematics (AREA)
  • Engineering & Computer Science (AREA)
  • General Engineering & Computer Science (AREA)
  • High Energy & Nuclear Physics (AREA)
  • Chemical & Material Sciences (AREA)
  • Dispersion Chemistry (AREA)
  • Packages (AREA)
  • Laminated Bodies (AREA)
  • Filling Or Discharging Of Gas Storage Vessels (AREA)
  • Particle Accelerators (AREA)
  • Refuse Collection And Transfer (AREA)
  • Processing Of Solid Wastes (AREA)
EP87107997A 1986-06-20 1987-06-03 Système à récipients doubles pour le transport et le stockage de matériaux radioactifs Withdrawn EP0250902A3 (fr)

Applications Claiming Priority (2)

Application Number Priority Date Filing Date Title
DE3620737 1986-06-20
DE3620737A DE3620737C1 (de) 1986-06-20 1986-06-20 Doppelbehaeltersystem zum Transport und zur Lagerung von radioaktiven Stoffen

Publications (2)

Publication Number Publication Date
EP0250902A2 true EP0250902A2 (fr) 1988-01-07
EP0250902A3 EP0250902A3 (fr) 1988-10-12

Family

ID=6303361

Family Applications (1)

Application Number Title Priority Date Filing Date
EP87107997A Withdrawn EP0250902A3 (fr) 1986-06-20 1987-06-03 Système à récipients doubles pour le transport et le stockage de matériaux radioactifs

Country Status (7)

Country Link
US (1) US4783309A (fr)
EP (1) EP0250902A3 (fr)
JP (1) JPS635300A (fr)
KR (1) KR880000982A (fr)
BR (1) BR8703085A (fr)
CA (1) CA1259141A (fr)
DE (1) DE3620737C1 (fr)

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DE3804276A1 (de) * 1988-02-11 1989-08-24 Wiederaufarbeitung Von Kernbre Vorrichtung zum verschrauben zweier komponenten, die hohes gewicht und eine gemeinsame vertikale achse haben, insbesondere zum verschrauben eines deckels mit einem behaelter zum transport und/oder lagerung von radioaktiven stoffen
US5225114A (en) * 1991-09-18 1993-07-06 Chem-Nuclear Systems, Inc. Multipurpose container for low-level radioactive waste
US5337917A (en) * 1991-10-21 1994-08-16 Sandia Corporation Crash resistant container
DE4135066C1 (fr) * 1991-10-24 1993-04-01 Gns Gesellschaft Fuer Nuklear-Service Mbh, 4300 Essen, De
US5303836A (en) * 1993-07-21 1994-04-19 The Babcock & Wilcox Company Shipping container for highly enriched uranium
JPH09211192A (ja) * 1996-01-30 1997-08-15 Sumitomo Metal Mining Co Ltd 核燃料物質の輸送方法
GB9609304D0 (en) * 1996-05-03 1996-07-10 British Nuclear Fuels Plc Improvements in and relating to fuel transportation
US20010011711A1 (en) * 1996-05-03 2001-08-09 Graham Nicholson Container for nuclear fuel transportation
EP0970478B1 (fr) 1996-08-30 2002-04-24 ICN Pharmaceuticals, Inc. Emballage avec tube a centrifugation
FR2776118B1 (fr) 1998-03-13 2000-06-09 Transnucleaire Dispositif de protection contre les rayonnements pour conteneur de transport de matieres radioactives
DE19856685A1 (de) * 1998-12-09 2000-06-15 Gnb Gmbh Abschirmbehälter
US6303956B1 (en) 1999-02-26 2001-10-16 Micron Technology, Inc. Conductive container structures having a dielectric cap
US6323501B1 (en) 1999-03-12 2001-11-27 Theragenics Corporation Container for storing and shipping radioactive materials
JP4296645B2 (ja) * 1999-08-10 2009-07-15 三菱マテリアル株式会社 核燃料物質貯蔵容器、中性子遮蔽材及びその製造方法
US6784443B2 (en) * 2000-01-11 2004-08-31 Nac International, Inc Storage vessels and related closure methods
US6472675B2 (en) 2000-12-15 2002-10-29 Theragenics Corporation Container for storing and shipping needle cartridges
JP3951685B2 (ja) * 2001-11-30 2007-08-01 株式会社日立製作所 中性子遮蔽材及び使用済み燃料収納容器
KR100473389B1 (ko) * 2002-04-26 2005-03-08 한국수력원자력 주식회사 방사성 물질 저장 및 운반 용기
US6989543B2 (en) 2003-08-15 2006-01-24 C.R. Bard, Inc. Radiation shielding container for radioactive sources
US7199375B2 (en) * 2004-10-12 2007-04-03 Bard Brachytherapy, Inc. Radiation shielding container that encloses a vial of one or more radioactive seeds
US7342989B2 (en) * 2005-06-23 2008-03-11 Nac International, Inc. Apparatuses and methods for mechanical shielding and cooling
KR101040250B1 (ko) 2009-03-05 2011-06-09 삼영에스엠주식회사 의료용 방사성 캡슐의 납용기
FR2952468B1 (fr) * 2009-11-10 2012-01-13 Tn Int Emballage pour le transport et/ou entreposage de matieres radioactives comprenant des elements de protection radiologique empiles radialement
CA2858381C (fr) 2011-12-08 2020-03-24 Atomic Energy Of Canada Limited/Energie Atomique Du Canada Limitee Appareil pour maintenir des objets radioactifs
JP6253881B2 (ja) * 2012-11-30 2017-12-27 三菱重工業株式会社 放射性物質収納用バスケット及び放射性物質収納容器
EP2827336B1 (fr) * 2013-07-15 2015-10-28 GNS Gesellschaft für Nuklear-Service mbH Récipient de transport et/ou de stockage
WO2015051076A1 (fr) 2013-10-02 2015-04-09 Nac International, Inc. Systèmes et procédés de transfert de combustible nucléaire épuisé depuis un lieu de stockage humide vers un lieu de stockage sec
US9793021B2 (en) 2014-01-22 2017-10-17 Nac International Inc. Transfer cask system having passive cooling
EP2975614B1 (fr) * 2014-07-17 2017-08-30 GNS Gesellschaft für Nuklear-Service mbH Récipient de transport et/ou de stockage, dispositif de montage et procédé de fermeture d'un récipient de transport et/ou de stockage

Citations (4)

* Cited by examiner, † Cited by third party
Publication number Priority date Publication date Assignee Title
FR2366674A1 (fr) * 1976-09-30 1978-04-28 Atomic Energy Authority Uk Recipient de transport de matieres radioactives
DE2749690A1 (de) * 1977-11-07 1979-05-10 Ganuk Ges Zur Auslegung Von Nu Transportbehaelter fuer abgebrannte kernreaktor-brennelemente
FR2431754A1 (fr) * 1978-07-19 1980-02-15 Transnuklear Gmbh Conteneur blinde pour le transport et/ou le stockage d'elements combustibles irradies
DE3144117A1 (de) * 1981-11-06 1983-05-19 Deutsche Gesellschaft für Wiederaufarbeitung von Kernbrennstoffen mbH, 3000 Hannover Betonschutzgehaeuse zur trockenen zwischenlagerung von brennelementbehaeltern

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US3780306A (en) * 1971-05-27 1973-12-18 Nat Lead Co Radioactive shipping container with neutron and gamma absorbers
FR2208165B1 (fr) * 1972-11-28 1975-09-12 Robatel Slpi
US3935467A (en) * 1973-11-09 1976-01-27 Nuclear Engineering Co., Inc. Repository for fissile materials
DE7911030U1 (de) * 1979-04-14 1979-08-23 Transnuklear Gmbh, 6450 Hanau Abschirmbehaelter zum transport und/ oder zur lagerung abgebrannter brennelemente
DE3012256A1 (de) * 1980-03-29 1981-10-15 Transnuklear Gmbh, 6450 Hanau Behaelter zum transport und/oder lagerung radioaktiver stoffe
DD208500A3 (de) * 1982-09-09 1984-05-02 Freiberg Brennstoffinst Lagerbecken fuer abgebrannte brennelemente
DE3430243C2 (de) * 1984-08-17 1986-11-27 Deutsche Gesellschaft für Wiederaufarbeitung von Kernbrennstoffen mbH, 3000 Hannover Lagerbehälter zur Aufnahme von vereinzelten Brennstäben bestrahlter Kernreaktorbrennelemente

Patent Citations (4)

* Cited by examiner, † Cited by third party
Publication number Priority date Publication date Assignee Title
FR2366674A1 (fr) * 1976-09-30 1978-04-28 Atomic Energy Authority Uk Recipient de transport de matieres radioactives
DE2749690A1 (de) * 1977-11-07 1979-05-10 Ganuk Ges Zur Auslegung Von Nu Transportbehaelter fuer abgebrannte kernreaktor-brennelemente
FR2431754A1 (fr) * 1978-07-19 1980-02-15 Transnuklear Gmbh Conteneur blinde pour le transport et/ou le stockage d'elements combustibles irradies
DE3144117A1 (de) * 1981-11-06 1983-05-19 Deutsche Gesellschaft für Wiederaufarbeitung von Kernbrennstoffen mbH, 3000 Hannover Betonschutzgehaeuse zur trockenen zwischenlagerung von brennelementbehaeltern

Also Published As

Publication number Publication date
US4783309A (en) 1988-11-08
JPS635300A (ja) 1988-01-11
CA1259141A (fr) 1989-09-05
KR880000982A (ko) 1988-03-30
DE3620737C1 (de) 1987-10-01
EP0250902A3 (fr) 1988-10-12
BR8703085A (pt) 1988-03-08

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