EP0036954B1 - Conteneur pour le transport et le stockage de matières radioactives - Google Patents

Conteneur pour le transport et le stockage de matières radioactives Download PDF

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Publication number
EP0036954B1
EP0036954B1 EP81101461A EP81101461A EP0036954B1 EP 0036954 B1 EP0036954 B1 EP 0036954B1 EP 81101461 A EP81101461 A EP 81101461A EP 81101461 A EP81101461 A EP 81101461A EP 0036954 B1 EP0036954 B1 EP 0036954B1
Authority
EP
European Patent Office
Prior art keywords
graphite
container according
container
inner lining
neutron
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
Application number
EP81101461A
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German (de)
English (en)
Other versions
EP0036954A1 (fr
Inventor
Richard Dr. Dr.-Ing. Christ
Klaus Ing. Grad. Wegner
Hartmut Dipl.-Phys. Kroll
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.)
Transnuklear GmbH
Original Assignee
Transnuklear GmbH
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 Transnuklear GmbH filed Critical Transnuklear GmbH
Publication of EP0036954A1 publication Critical patent/EP0036954A1/fr
Application granted granted Critical
Publication of EP0036954B1 publication Critical patent/EP0036954B1/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
    • G21F5/06—Details of, or accessories to, the 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
    • 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 container for transport and / or storage of radioactive materials, the ⁇ - and n-emit radiation, and generate significant residual heat, consisting of a container body with shielding function ⁇ - and n-radiation and an inner liner.
  • Containers that are used for the transport and / or storage of spent fuel elements must safely contain the radioactivity of the goods brought in and demonstrate in rigorous tests that this is guaranteed even in extreme accident situations. At the same time, however, they must also shield the gamma and neutron beams released during the radioactive decay reactions and dissipate the heat of decay to the outside. The shielding function must remain largely intact even after an accident, its integrity must be easily verifiable.
  • Known shielding containers usually consist of a metallic base container with the required mechanical strength and the wall thickness required to shield the gamma rays, usually made of steel, and an outer shell made of neutron shielding material, mostly with organic substances high hydrogen content or in the form of a water jacket.
  • a disadvantage of these constructions is that even slight collisions of the container, as can also occur during routine operation, can damage the neutron shielding and afterwards require extensive repair of the entire container. In the event of a serious accident, characterized by high impact forces and exposure to fire, this neutron shielding can fail completely and the dose rate in the vicinity of the container can increase.
  • DE-B2-2 040 348 also describes a container in which the neutron shield is arranged in the base body under the outer skin.
  • a container is also known from DE-A-2 019 446, in which neutron shielding material is arranged in the y absorption layer. Both container designs have the disadvantage that the neutron shielding layer is not freely accessible and cannot be inspected and, if necessary, repaired after an accident. Even in the event of a fire, this neutron shielding material is endangered and can easily be destroyed or ineffective.
  • a container for the transport and / or storage of radioactive substances, in particular for irradiated nuclear fuel elements and highly active waste consisting of a base body with a shielding function for ⁇ and n radiation and an inner lining made of corrosion-resistant Material which has a further n-shield that is resistant to the effects of external accidents, in order to maintain sufficient shielding effect in the event of loss or damage to the outer n-shield.
  • this additional shielding should not hinder the dissipation of the decay heat from the interior of the container.
  • the n-shield should be easily accessible and easy to repair.
  • n-shield in the form of a graphite-based material is additionally arranged between the inner lining and the base body.
  • the inventive position of the additional n-shield within the solid base body ensures the best possible protection against mechanical and thermal damage, the shield is easily accessible, inspectable and repairable.
  • the use of graphite according to the invention provides additional n-shielding and at the same time fulfills the requirement of good thermal conductivity. Furthermore, there is excellent resistance to elevated temperatures, such as those which occur during normal operation of the container and in particular when exposed to an accident fire.
  • the moderating properties of graphite have the additional advantage that neutron activation of the container body is largely prevented.
  • the n-shielding layers on the outside of the base body and the inner n-shielding according to the invention can be dimensioned such that, depending on the requirements, the inner or outer shielding layer makes the predominant contribution to shielding against neutron beams under normal operating conditions.
  • I and 111 illustrate the invention in more detail schematically and by way of example.
  • the transport and / or storage container consists of a base body 1, for example made of steel, on which cooling fins 2 and an outer n-shield 3 are arranged in a manner known per se.
  • the interior 4 of the container for receiving the radioactive material is formed by the inner lining 5 made of corrosion-resistant material, for example stainless steel, and a shielding cover 6, which also carries n-shielding material 3 on its outside.
  • the cover zone is protected against mechanical and thermal influences by a protective hood 7.
  • n-shielding layer 8 made of a graphite-based material as a further neutron shield orderly.
  • This graphite-based shielding layer 8 preferably consists of a mixture of graphite powder and a hardening binder, such as, for example, water glass or, above all, a casting resin.
  • This mixture can either be introduced as such into the annular gap between the base body 1 and the inner lining 5 and hardened, or it can advantageously be prefabricated graphite moldings 9, z. B. in the manner of composite plasters that are adapted to the gap dimensions can be used. These shaped pieces can also be covered with a metallic jacket 10, preferably made of neutron-absorbing material. It is also possible to press a stampable graphite mass into the annular gap.
  • the function of the inner lining 5 can be taken over in a particularly advantageous manner by the metallic shells 10 which surround the graphite shaped pieces 9.
  • the separate inner lining 5 can then be omitted partially or completely.
  • the GraphicsGro t formstük- ke 9 are particularly low attached to the inside of the base body 1, for example by guide rails 12.
  • the shielding layer 8 can be easily adapted to the respective requirements by changing graphite moldings 9 of different thicknesses.

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  • Physics & Mathematics (AREA)
  • Engineering & Computer Science (AREA)
  • General Engineering & Computer Science (AREA)
  • High Energy & Nuclear Physics (AREA)
  • Laminated Bodies (AREA)
  • Filling Or Discharging Of Gas Storage Vessels (AREA)
  • Packages (AREA)

Claims (10)

1. Cuve de transport et/ou de stockage pour matières radioactives, en particulier des éléments combustibles nucléaires irradiés, et des déchets à radioactivité élevée, constituée par un corps de base ayant une fonction de blindage contre les radiations p et n, et une garniture intérieure en matériau résistant à la corrosion, cuve caractérisée en ce qu'il est disposé, en outre, entre la garniture intérieure (5) et le corps de base (1), une couche de blindage contre les neutrons (8) sous forme d'un matériau à base de graphite.
2. Cuve selon la revendication 1, caractérisée en ce que le matériau est constitué par un mélange durcissable de poudre de graphite et d'un liant.
3. Cuve selon l'une quelconque des revendications 1 ou 2, caractérisée en ce que le matériau est constitué par un mélange durcissable de poudre de graphite et de résine apte à être coulée.
4. Cuve selon l'une quelconque des revendications 1 à 3, caractérisée en ce que la protection est constituée par des pièces moulées (9) en graphite.
5. Cuve selon la revendication 4, caractérisée en ce que les pièces moulées (9) en graphite sont entourées d'une gaine métallique (10).
6. Cuve selon la revendication 5, caractérisée en ce que la gaine métallique (10) représente en même temps la garniture intérieure 5.
7. Cuve selon les revendications 4 à 6, caractérisée en ce que les pièces moulées (9) en graphite sont fixées sur la face intérieure du corps de base (1).
8. Cuve selon l'une quelconque des revendications 1 à 7, caractérisée en ce que le matériau à base de graphite est mélangé en outre avec une matière absorbant les neutrons.
9. Cuve selon la revendication 8, caractérisée en ce que la matière absorbant les neutrons introduite dans le mélange est du carbure de bore en poudre.
10. Cuve selon l'une quelconque des revendications 1 à 9, caractérisée en ce que la garniture intérieure (5) est fixée sur le corps de base (1) au moyen de tirauts (11).
EP81101461A 1980-03-29 1981-02-28 Conteneur pour le transport et le stockage de matières radioactives Expired EP0036954B1 (fr)

Applications Claiming Priority (2)

Application Number Priority Date Filing Date Title
DE3012256 1980-03-29
DE19803012256 DE3012256A1 (de) 1980-03-29 1980-03-29 Behaelter zum transport und/oder lagerung radioaktiver stoffe

Publications (2)

Publication Number Publication Date
EP0036954A1 EP0036954A1 (fr) 1981-10-07
EP0036954B1 true EP0036954B1 (fr) 1984-06-06

Family

ID=6098736

Family Applications (1)

Application Number Title Priority Date Filing Date
EP81101461A Expired EP0036954B1 (fr) 1980-03-29 1981-02-28 Conteneur pour le transport et le stockage de matières radioactives

Country Status (4)

Country Link
US (1) US4453081A (fr)
EP (1) EP0036954B1 (fr)
DE (1) DE3012256A1 (fr)
ES (1) ES8305147A1 (fr)

Cited By (1)

* Cited by examiner, † Cited by third party
Publication number Priority date Publication date Assignee Title
RU2722214C1 (ru) * 2019-09-13 2020-05-28 Общество с ограниченной ответственностью "Керамические технологии" Контейнер для хранения, транспортирования и захоронения радиоактивных отходов

Families Citing this family (25)

* Cited by examiner, † Cited by third party
Publication number Priority date Publication date Assignee Title
DE3012256A1 (de) * 1980-03-29 1981-10-15 Transnuklear Gmbh, 6450 Hanau Behaelter zum transport und/oder lagerung radioaktiver stoffe
DE3149945A1 (de) * 1981-12-17 1983-07-21 Deutsche Gesellschaft für Wiederaufarbeitung von Kernbrennstoffen mbH, 3000 Hannover Behaelter fuer die langzeitlagerung von abgebrannten kernreaktorbrennelementen
EP0116412A1 (fr) * 1983-01-18 1984-08-22 Kabushiki Kaisha Kobe Seiko Sho Récipient pour matériaux radioactifs et méthode pour sa fabrication
DE3324291C2 (de) * 1983-07-06 1986-10-23 Deutsche Gesellschaft für Wiederaufarbeitung von Kernbrennstoffen mbH, 3000 Hannover Verfahren zum Befüllen von Metallbehältern mit einer radioaktiven Glasschmelze und Vorrichtung zur Aufnahme einer radioaktiven Glasschmelze
HU191255B (en) * 1984-03-05 1987-01-28 Eroemue- Es Halozattervezoe Vallalat,Hu Container for transporting radioactive matters
DE3445124C1 (de) * 1984-12-11 1986-01-23 Nukem Gmbh, 6450 Hanau Auskleidung fuer Bohrloecher in Salzstoecken
US4751021A (en) * 1985-12-30 1988-06-14 Aar Corporation Bendable sheet material
DE3620737C1 (de) * 1986-06-20 1987-10-01 Wiederaufarbeitung Von Kernbre Doppelbehaeltersystem zum Transport und zur Lagerung von radioaktiven Stoffen
WO1989002153A1 (fr) * 1987-09-02 1989-03-09 Chem-Nuclear Systems, Inc. Fut en fonte ductile avec uranium, tungstene encapsules ou autres protections metalliques denses
GB8729504D0 (en) * 1987-12-18 1988-02-03 British Nuclear Fuels Plc Transport & storage flask
US5406600A (en) * 1993-10-08 1995-04-11 Pacific Nuclear Systems, Inc. Transportation and storage cask for spent nuclear fuels
JP3342994B2 (ja) * 1995-08-04 2002-11-11 株式会社神戸製鋼所 放射性物質の輸送兼貯蔵用容器
US5944190A (en) * 1997-05-30 1999-08-31 Mallinckrodt Inc. Radiopharmaceutical capsule safe
US6332906B1 (en) 1998-03-24 2001-12-25 California Consolidated Technology, Inc. Aluminum-silicon alloy formed from a metal powder
US5965829A (en) * 1998-04-14 1999-10-12 Reynolds Metals Company Radiation absorbing refractory composition
US6495846B1 (en) * 1999-02-25 2002-12-17 James A. Vaughan Apparatus and method for nuclear waste storage
DE60336743D1 (de) 2002-10-17 2011-05-26 Mallinckrodt Inc Vorrichtung zum transport von flüssigen radiopharmazeutika und die damit verbundene anwendungs- und herstellungsmethode
ATE385607T1 (de) * 2002-12-24 2008-02-15 Nuklear Service Gmbh Gns Transport- und lagerbehälter für wärmeentwickelnde radioaktive stoffe, insbesondere abgebrannte kernreaktorbrennelemente oder haw-glaskokillen
WO2008077004A1 (fr) * 2006-12-18 2008-06-26 Medi-Physics, Inc. Conteneur blindé
US8535604B1 (en) 2008-04-22 2013-09-17 Dean M. Baker Multifunctional high strength metal composite materials
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
DE102010000974A1 (de) 2010-01-18 2011-07-21 ALD Vacuum Technologies GmbH, 63450 Form-, strahlungs- und temperaturstabiler Körper, geeignet zum Transport und/oder zur Lagerung von radioaktiven Abfällen
FR2961005B1 (fr) * 2010-06-02 2015-12-11 Tn Int Emballage pour le transport et/ou entreposage de matieres radioactives, comprenant des moyens de conduction thermique ameliores
US20190066858A1 (en) * 2017-08-31 2019-02-28 Nac International Inc. Containment cask for drum containing radioactive hazardous waste
US11602788B2 (en) 2018-05-04 2023-03-14 Dean Baker Dissolvable compositions and tools including particles having a reactive shell and a non-reactive core

Family Cites Families (10)

* Cited by examiner, † Cited by third party
Publication number Priority date Publication date Assignee Title
CH492656A (de) * 1966-08-09 1970-06-30 Marxen Friedrich Gegen radioaktive Strahlen, insbesondere Gamma- und Neutronenstrahlen, abschirmender Baustoff und Verfahren zu seiner Herstellung
FR1568883A (fr) * 1968-02-09 1969-05-30
DE1807421A1 (de) * 1968-04-19 1969-11-06 Atomic Power Construction Ltd Biologische Abschirmung fuer einen Kernreaktor
JPS5419560B1 (fr) * 1969-08-13 1979-07-16
FR2074726A7 (en) * 1970-01-22 1971-10-08 Robatel Slpi Composite packaging material esp - for radio chemicals
FR2208165B1 (fr) * 1972-11-28 1975-09-12 Robatel Slpi
DE2631769B2 (de) * 1976-07-15 1979-08-02 Steag Kernenergie Gmbh, 4300 Essen Vorrichtung für die Endlagerung von radioaktiven Abfallstoffen verschiedener Aktivitäten
DE2740933C2 (de) * 1977-09-10 1982-11-25 GNS Gesellschaft für Nuklear-Service mbH, 4300 Essen Transport- bzw. Lagerbehälter für radioaktive Stoffe, insbesondere bestrahlte Kernreaktorbrennelemente
US4225467A (en) * 1977-11-25 1980-09-30 The Carborundum Company Neutron absorbing article and method for manufacture of such article
DE3012256A1 (de) * 1980-03-29 1981-10-15 Transnuklear Gmbh, 6450 Hanau Behaelter zum transport und/oder lagerung radioaktiver stoffe

Cited By (1)

* Cited by examiner, † Cited by third party
Publication number Priority date Publication date Assignee Title
RU2722214C1 (ru) * 2019-09-13 2020-05-28 Общество с ограниченной ответственностью "Керамические технологии" Контейнер для хранения, транспортирования и захоронения радиоактивных отходов

Also Published As

Publication number Publication date
US4453081A (en) 1984-06-05
DE3012256A1 (de) 1981-10-15
ES8305147A1 (es) 1983-03-16
EP0036954A1 (fr) 1981-10-07

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