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EP0079469A1 - Récipient de protection en béton pour le stockage des conteneurs d'éléments combustibles - Google Patents

Récipient de protection en béton pour le stockage des conteneurs d'éléments combustibles Download PDF

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Publication number
EP0079469A1
EP0079469A1 EP82109599A EP82109599A EP0079469A1 EP 0079469 A1 EP0079469 A1 EP 0079469A1 EP 82109599 A EP82109599 A EP 82109599A EP 82109599 A EP82109599 A EP 82109599A EP 0079469 A1 EP0079469 A1 EP 0079469A1
Authority
EP
European Patent Office
Prior art keywords
protective housing
concrete protective
concrete
fuel element
fuel
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
EP82109599A
Other languages
German (de)
English (en)
Other versions
EP0079469B1 (fr
Inventor
Hans-Peter Dipl.-Phys. Dyck
Harry Dipl.-Ing. Spilker
Heinz-Dieter Gregor
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 EP0079469A1 publication Critical patent/EP0079469A1/fr
Application granted granted Critical
Publication of EP0079469B1 publication Critical patent/EP0079469B1/fr
Expired legal-status Critical Current

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Classifications

    • GPHYSICS
    • G21NUCLEAR PHYSICS; NUCLEAR ENGINEERING
    • G21FPROTECTION AGAINST X-RADIATION, GAMMA RADIATION, CORPUSCULAR RADIATION OR PARTICLE BOMBARDMENT; TREATING RADIOACTIVELY CONTAMINATED MATERIAL; DECONTAMINATION ARRANGEMENTS THEREFOR
    • G21F5/00Transportable or portable shielded containers
    • G21F5/005Containers for solid radioactive wastes, e.g. for ultimate disposal
    • G21F5/008Containers for fuel elements
    • GPHYSICS
    • G21NUCLEAR PHYSICS; NUCLEAR ENGINEERING
    • G21FPROTECTION AGAINST X-RADIATION, GAMMA RADIATION, CORPUSCULAR RADIATION OR PARTICLE BOMBARDMENT; TREATING RADIOACTIVELY CONTAMINATED MATERIAL; DECONTAMINATION ARRANGEMENTS THEREFOR
    • G21F5/00Transportable or portable shielded containers
    • G21F5/06Details of, or accessories to, the containers
    • G21F5/10Heat-removal systems, e.g. using circulating fluid or cooling fins

Definitions

  • the invention relates to a concrete protective housing for receiving and storing a fuel element storage container that is loaded with spent nuclear reactor fuel elements and is suitable for transport and storage, the clear dimensions of the concrete protective housing being somewhat larger than the external dimensions of the fuel element container.
  • silo containers made of concrete or reinforced concrete.
  • These silo containers forming a concrete protective housing can have different designs.
  • the protective container has lateral supply air ducts on the lower edge of the casing and lateral exhaust air ducts in the region of the upper casing edge below the cover (patent application P 30 17 767.4).
  • the arrangement of these exhaust air and supply air channels results in natural convection within the concrete protective housing, which is used to dissipate the residual heat.
  • the invention is based on the object of designing a concrete protective housing for receiving fuel element containers in such a way that simple monitoring of the fuel element containers is possible during their intermediate storage.
  • the object is achieved in that measuring probes embedded in the concrete are arranged on the inside of the casing of the concrete protective housing.
  • the the B race element container monitoring probes are now already before loading the concrete protective housing with the fuel element container. Cumbersome and time-consuming mounting of the measuring devices can be omitted.
  • the measuring probes and their electrical connection lines can already be cast into the concrete housing.
  • An advantageous embodiment of the invention is characterized by the features of the claim. 2 suggested.
  • the radial ventilation openings that deviate from the horizontal increase natural convection while simultaneously reducing the radiation emission.
  • the temperature sensors attached at different heights can detect a temperature profile that may arise differently due to the radial ventilation holes.
  • the concrete protective housing consists of a base part 3 in the form of a pallet, a cylindrical concrete protective jacket 4 placed thereon and a cylindrical cover 5 lying on the concrete protective jacket 4.
  • the foot part 3 consists of a square base plate 6, at the corners of which a foot 7 is arranged, so that the foot part 3 is designed as a pallet that can be driven under.
  • the cylindrical concrete jacket 4 is placed on the foot part 3 and aligned to the foot part 3 by suitable centering devices (not shown here). '
  • the concrete protective jacket 4 has recesses 9 at its lower end, which serve as supply air channels.
  • the cover 5 lying on the concrete protective jacket 4 also has recesses 11 in the edge area on its surface facing the jacket 4, which serve as exhaust air ducts.
  • a fuel element container 12 shown here in broken lines, is arranged upright.
  • the container jacket 4 is radially inclined from the horizontal Fill openings 13 penetrated. At different heights, temperature guides 14 are let into the inside of the container jacket, which are connected via corresponding electrical connecting lines 15 to a connection 16 located on the outside of the container jacket 4.
  • the fuel assembly 12 When the fuel assembly 12 is delivered to the intermediate storage facility, the fuel assembly 12 is placed on the base plate 6 of the foot part 3. The concrete protective jacket 4 is then placed over the base part 3 over the fuel element container 12.
  • the contents of the entire concrete protective housing 3, 4, 5 are now moved to the storage area by means of a suitable lifting truck, which is preferably located outdoors.
  • a suitable lifting truck which is preferably located outdoors.
  • the electrical connection between the temperature sensor 14 monitoring the temperature inside the concrete protective housing and the overall monitoring system can be established by a simple plug connection on the outer surface of the container shell 4.
  • the temperature sensors 14 and the electrical connecting lines 15 can already be inserted into the mold during the production of the concrete protective jacket 4, so that they are enclosed by the setting molding compound.

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)
  • Measuring Temperature Or Quantity Of Heat (AREA)
  • Details Of Rigid Or Semi-Rigid Containers (AREA)
  • Packages (AREA)
  • Containers Having Bodies Formed In One Piece (AREA)
EP82109599A 1981-11-05 1982-10-18 Récipient de protection en béton pour le stockage des conteneurs d'éléments combustibles Expired EP0079469B1 (fr)

Applications Claiming Priority (2)

Application Number Priority Date Filing Date Title
DE3143865 1981-11-05
DE19813143865 DE3143865A1 (de) 1981-11-05 1981-11-05 Betonschutzgehaeuse zur aufnahme von brennelementbehaeltern

Publications (2)

Publication Number Publication Date
EP0079469A1 true EP0079469A1 (fr) 1983-05-25
EP0079469B1 EP0079469B1 (fr) 1985-05-29

Family

ID=6145639

Family Applications (1)

Application Number Title Priority Date Filing Date
EP82109599A Expired EP0079469B1 (fr) 1981-11-05 1982-10-18 Récipient de protection en béton pour le stockage des conteneurs d'éléments combustibles

Country Status (5)

Country Link
US (1) US4532428A (fr)
EP (1) EP0079469B1 (fr)
JP (1) JPS58135495A (fr)
CA (1) CA1187631A (fr)
DE (2) DE3143865A1 (fr)

Families Citing this family (31)

* Cited by examiner, † Cited by third party
Publication number Priority date Publication date Assignee Title
EP0162839A1 (fr) * 1983-11-22 1985-12-04 CANEVALL, John Procedure de stockage temporaire de materiau radio-actif
JPS6117996A (ja) * 1984-07-04 1986-01-25 株式会社日立製作所 発熱性放射性物質の貯蔵方法
US4636358A (en) * 1985-02-04 1987-01-13 The United States Of America As Represented By The Secretary Of The Navy Concretization of high level radioactive source in marine sediment
US4780269A (en) * 1985-03-12 1988-10-25 Nutech, Inc. Horizontal modular dry irradiated fuel storage system
FR2601809B1 (fr) * 1986-07-17 1988-09-16 Commissariat Energie Atomique Dispositif de stockage a sec de materiaux degageant de la chaleur, notamment de materiaux radioactifs
US4800062A (en) * 1987-02-23 1989-01-24 Nuclear Packaging, Inc. On-site concrete cask storage system for spent nuclear fuel
US5733066A (en) * 1992-09-14 1998-03-31 Myers; Lawrence S. Apparatus and method for disposal of nuclear and other hazardous wastes
US5545796A (en) * 1994-02-25 1996-08-13 Scientific Ecology Group Article made out of radioactive or hazardous waste and a method of making the same
JP2002202396A (ja) * 2000-12-27 2002-07-19 Mitsubishi Heavy Ind Ltd 放射性物質を収納した密閉容器の温度制御方法、この密閉容器を貯蔵する貯蔵システムおよび貯蔵施設
US8098790B2 (en) * 2004-03-18 2012-01-17 Holtec International, Inc. Systems and methods for storing spent nuclear fuel
US7590213B1 (en) 2004-03-18 2009-09-15 Holtec International, Inc. Systems and methods for storing spent nuclear fuel having protection design
US8718220B2 (en) 2005-02-11 2014-05-06 Holtec International, Inc. Manifold system for the ventilated storage of high level waste and a method of using the same to store high level waste in a below-grade environment
WO2006086766A2 (fr) * 2005-02-11 2006-08-17 Holtec International, Inc. Systeme collecteur destine a un stockage aere de dechets a activite elevee et procede d'utilisation de ce systeme afin de stocker des dechets a activite elevee dans un environnement souterrain
US9443625B2 (en) 2005-03-25 2016-09-13 Holtec International, Inc. Method of storing high level radioactive waste
US7330526B2 (en) 2005-03-25 2008-02-12 Holtec International, Inc. System and method of storing high level waste
ES2310449B1 (es) * 2006-06-29 2009-11-06 Ecopiro, S.L. Contenedor con capsula de seguridad para almacenar elementos de pirotecnia de salvamento.
WO2009117037A2 (fr) 2007-12-22 2009-09-24 Holtec International, Inc. Système et procédé pour le stockage ventilé de déchets radioactifs de haut niveau dans un agencement regroupé
US9001958B2 (en) 2010-04-21 2015-04-07 Holtec International, Inc. System and method for reclaiming energy from heat emanating from spent nuclear fuel
US11569001B2 (en) 2008-04-29 2023-01-31 Holtec International Autonomous self-powered system for removing thermal energy from pools of liquid heated by radioactive materials
RU2525229C2 (ru) 2009-05-06 2014-08-10 Холтек Интернэшнл, Инк. Устройство для хранения и/или транспортировки высокорадиоактивных отходов, а также способ его изготовления
WO2013158914A1 (fr) 2012-04-18 2013-10-24 Holtec International, Inc. Stockage et/ou transfert de déchets hautement radioactifs
US11887744B2 (en) 2011-08-12 2024-01-30 Holtec International Container for radioactive waste
US11373774B2 (en) 2010-08-12 2022-06-28 Holtec International Ventilated transfer cask
US9514853B2 (en) 2010-08-12 2016-12-06 Holtec International System for storing high level radioactive waste
US8905259B2 (en) 2010-08-12 2014-12-09 Holtec International, Inc. Ventilated system for storing high level radioactive waste
US10811154B2 (en) 2010-08-12 2020-10-20 Holtec International Container for radioactive waste
WO2013115881A2 (fr) * 2011-11-14 2013-08-08 Holtec International, Inc. Procédé de stockage de déchets radioactifs, et système pour sa mise en œuvre
US9105365B2 (en) 2011-10-28 2015-08-11 Holtec International, Inc. Method for controlling temperature of a portion of a radioactive waste storage system and for implementing the same
US10020084B2 (en) 2013-03-14 2018-07-10 Energysolutions, Llc System and method for processing spent nuclear fuel
US11715575B2 (en) 2015-05-04 2023-08-01 Holtec International Nuclear materials apparatus and implementing the same
CN111344809B (zh) 2017-11-03 2024-04-30 霍尔泰克国际公司 存储高水平放射性废料的方法

Citations (7)

* Cited by examiner, † Cited by third party
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
FR1393704A (fr) * 1963-04-03 1965-03-26 Nat Lead Co Récipient pour éléments de combustible
FR2181540A1 (fr) * 1972-04-27 1973-12-07 Commissariat Energie Atomique
FR2198224A1 (fr) * 1972-08-07 1974-03-29 Dubovsky Boris
FR2357478A1 (fr) * 1976-07-06 1978-02-03 Kernforschung Gmbh Ges Fuer Procede et installation de remplissage d'un reservoir avec un liquide radioactif
EP0039785A1 (fr) * 1980-05-09 1981-11-18 Deutsche Gesellschaft für Wiederaufarbeitung von Kernbrennstoffen mbH Dispositif pour le stockage, le transport et la protection contre les rayonnements des éléments combustibles usés
FR2495817A1 (fr) * 1980-12-06 1982-06-11 Kernforschungsz Karlsruhe Conteneur pour le stockage et le transport d'au moins une coquille remplie de dechets radio-actifs incorpores dans du verre fondu

Patent Citations (7)

* Cited by examiner, † Cited by third party
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
FR1393704A (fr) * 1963-04-03 1965-03-26 Nat Lead Co Récipient pour éléments de combustible
FR2181540A1 (fr) * 1972-04-27 1973-12-07 Commissariat Energie Atomique
FR2198224A1 (fr) * 1972-08-07 1974-03-29 Dubovsky Boris
FR2357478A1 (fr) * 1976-07-06 1978-02-03 Kernforschung Gmbh Ges Fuer Procede et installation de remplissage d'un reservoir avec un liquide radioactif
EP0039785A1 (fr) * 1980-05-09 1981-11-18 Deutsche Gesellschaft für Wiederaufarbeitung von Kernbrennstoffen mbH Dispositif pour le stockage, le transport et la protection contre les rayonnements des éléments combustibles usés
FR2495817A1 (fr) * 1980-12-06 1982-06-11 Kernforschungsz Karlsruhe Conteneur pour le stockage et le transport d'au moins une coquille remplie de dechets radio-actifs incorpores dans du verre fondu

Also Published As

Publication number Publication date
CA1187631A (fr) 1985-05-21
DE3143865A1 (de) 1983-05-11
US4532428A (en) 1985-07-30
EP0079469B1 (fr) 1985-05-29
DE3263916D1 (en) 1985-07-04
JPS58135495A (ja) 1983-08-12

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