EP0036954B1 - Container for transportation and storage of radioactive substances - Google Patents

Container for transportation and storage of radioactive substances 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
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EP
European Patent Office
Prior art keywords
graphite
container according
container
inner lining
neutron
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Expired
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EP81101461A
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German (de)
French (fr)
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EP0036954A1 (en
Inventor
Richard Dr. Dr.-Ing. Christ
Klaus Ing. Grad. Wegner
Hartmut Dipl.-Phys. Kroll
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Transnuklear GmbH
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Transnuklear GmbH
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Publication of EP0036954A1 publication Critical patent/EP0036954A1/en
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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
    • 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.

Description

Die Erfindung betrifft einen Behälter zum Transport und/oder Lagerung radioaktiver Stoffe, die γ- und n-Strahlung aussenden und nennenswerte Nachwärme erzeugen, bestehend aus einem Behälterkörper mit Abschirmfunktion für γ- und n-Strahlung und einer inneren Auskleidung.The invention relates to a container for transport and / or storage of radioactive materials, the γ- and n-emit radiation, and generate significant residual heat, consisting of a container body with shielding function γ - and n-radiation and an inner liner.

Behälter, die zum Transport und/oder Lagerung abgebrannter Brennelemente eingesetzt werden, müssen die Radioaktivität des eingebrachten Gutes sicher einschließen und in strengen Tests nachweisen, daß dies auch bei extremen Unfallsituationen gewährleistet ist. Gleichzeitig müssen sie aber auch die bei den radioaktiven Zerfallsreaktionen freiwerdenden Gamma-und Neutronenstrahlen abschirmen und die Zerfallswärme nach außen ableiten. Die Abschirmfunktion muß auch nach Unfallbeanspruchung weitgehend erhalten bleiben, ihre Integrität auf einfache Weise nachprüfbar sein.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.

Bekannte Abschirmbehälter (z. B. DE-B2-2 040 348) bestehen meist aus einem metallischen Grundbehälter mit der erforderlichen mechanischen Festigkeit und der zur Abschirmung der Gammastrahlen erforderlichen Wandstärke, gewöhnlich aus Stahl, und einer äußeren Schale aus Neutronenabschirmmaterial, meist organische Stoffe mit hohem Wasserstoffanteil oder in Form eines Wassermantels.Known shielding containers (e.g. DE-B2-2 040 348) 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.

Nachteilig bei diesen Konstruktionen ist, daß schon leichte Kollisionen des Behälters, wie sie auch beim routinemäßigen Betrieb vorkommen können, zur Beschädigung der Neutronenabschirmung führen können und danach eine aufwendige Reparatur des gesamten Behälters erforderlich machen. Bei einem schweren Unfall, charakterisiert durch hohe Stoßkräfte und Feuereinwirkung, kann diese Neutronenabschirmung völlig versagen und die Dosisleistung in der Umgebung des Behälters sich erhöhen.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.

Während die metallische i-Abschirmungswand erfahrungsgemäß bei schweren Unfällen erhalten bleibt, versagt die außenliegende Neutronenabschirmung infolge der mechanischen und thermischen Einwirkungen, mit der Folge eines entsprechenden Anstiegs der Neutronen-Dosisbelastung der Umgebung.Experience has shown that the metallic i-shielding wall is retained in the event of serious accidents, while the external neutron shielding fails due to the mechanical and thermal effects, with the result that the neutron dose load in the environment increases accordingly.

In der DE-B2-2 040 348 wird auch ein Behälter beschrieben, bei dem die Neutronenabschirmung im Grundkörper unter der Außenhaut angeordnet ist. Ebenso ist aus der DE-A-2 019 446 ein Behälter bekannt, bei dem in der y-Absorptionsschicht Neutronenabschirmmaterial angeordnet ist. Beide Behälterkonzeptionen haben den Nachteil, daß die Neutronenabschirmschicht nicht frei zugänglich ist und nach einem Unfall nicht inspiziert und gegebenenfalls repariert werden kann. Auch bei einem Brand ist dieses Neutronenabschirmmaterial gefährdet und kann leicht zerstört bzw. unwirksam werden.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.

Es war deshalb die Aufgabe der vorliegenden Erfindung, einen Behälter zum Transport und/ oder Lagerung radioaktiver Stoffe, insbesondere für bestrahlte Kernbrennstoffelemente und hochaktiven Abfall, zu schaffen, bestehend aus einem Grundkörper mit Abschirmfunktion für γ-und n-Strahlung und einer inneren Auskleidung aus korrosionsbeständigem Material der eine weitere, gegen die Einwirkung von äußeren Unfällen beständige n-Abschirmung aufweist, um bei Verlust oder Beschädigung der äußeren n-Abschirmung noch ausreichende Abschirmwirkung aufrechtzuerhalten. Diese zusätzliche Abschirmung sollte aber die Ableitung der Zerfallswärme aus dem Behälterinnenraum nicht behindern. Außerdem sollte die n-Abschirmung leicht zugänglich und reparaturfreundlich sein.It was therefore the object of the present invention to create 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 γ 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. However, this additional shielding should not hinder the dissipation of the decay heat from the interior of the container. In addition, the n-shield should be easily accessible and easy to repair.

Diese Aufgabe wird erfindungsgemäß dadurch gelöst, daß zusätzlich eine n-Abschirmung in Form eines Materials auf Graphitbasis zwischen der inneren Auskleidung und dem Grundkörper angeordnet ist.This object is achieved in that an n-shield in the form of a graphite-based material is additionally arranged between the inner lining and the base body.

Durch die erfindungsgemäße Lage der zusätzlichen n-Abschirmung innerhalb des massiven Grundkörpers ist ein bestmöglicher Schutz vor mechanischen und thermischen Beschädigungen gewährleistet, die Abschirmung ist leicht zugänglich, inspizierbar und reparierbar. Die erfindungsgemäße Verwendung von Graphit erwirkt mit seiner moderierenden Eigenschaft eine zusätzliche n-Abschirmung und erfüllt gleichzeitig die Anforderung guter Wärmeleitfähigkeit. Weiterhin ist eine hervorragende Beständigkeit bei erhöhten Temperaturen, wie sie im Normalbetrieb des Behälters und insbesondere bei der Einwirkung eines Unfallfeuers vorliegen, gegeben. Die moderierenden Eigenschaften des Graphits haben den zusätzlichen Vorteil, daß eine Neutronenaktivierung des Behältergrundkörpers weitgehend verhindert wird.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. With its moderating property, 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.

Die n-Abschirmschichten an der Außenseite des Grundkörpers und die erfindungsgemäße innere n-Abschirmung können so dimensioniert werden, daß je nach Erfordernis die innere oder äußere Abschirmschicht den überwiegenden Beitrag zur Abschirmung gegen Neutronenstrahlen unter normalen Betriebsbedingungen liefert. In den Abb. I, und 111 ist die Erfindung schematisch und beispielhaft näher erläutert. Der Transport- und/oder Lagerbehälter besteht aus einem Grundkörper 1, beispielsweise aus Stahl, an dem in an sich bekannter Weise Kühlrippen 2 und eine äußere n-Abschirmung 3 angeordnet sind. Der Innenraum 4 des Behälters zur Aufnahme des radioaktiven Materials wird gebildet von der inneren Auskleidung 5 aus korrosionsbeständigem Material, beispielsweise Edelstahl, und einem Abschirmdeckel 6, der an seiner Außenseite ebenfalls n-Abschirmmaterial 3 trägt. Die Dekkelzone ist durch eine Schutzhaube 7 gegen mechanische und thermische Einwirkungen geschützt.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.

Im Ringspalt zwischen der Auskleidung 5 und dem Grundkörper 1 ist zusätzlich eine n-Abschirmungsschicht 8 aus einem Material auf Graphitbasis als weitere Neutronenabschirmung angeordnet.In the annular gap between the lining 5 and the base body 1 there is additionally an n-shielding layer 8 made of a graphite-based material as a further neutron shield orderly.

Diese Abschirmungsschicht 8 auf Graphitbasis besteht vorzugsweise aus einer Mischung aus Graphitpulver und einem erhärtenden Bindemittel, wie beispielsweise Wasserglas oder vor allem einem Gießharz.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.

Dieses Gemisch kann entweder als solches in den Ringspalt zwischen Grundkörper 1 und innerer Auskleidung 5 eingebracht und ausgehärtet werden, oder es können vorteilhafterweise vorgefertigte Graphitformstücke 9, z. B. in der Art von Verbundpflaster, die den Spaltdimensionen angepaßt sind, eingesetzt werden. Dabei können diese Formstücke auch mit einem metallischen Mantel 10, vorzugsweise aus neutronenabsorbierendem Material, umkleidet werden. Auch ist es möglich, eine stampffähige Graphitmasse in den Ringspalt einzupressen.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.

Als besonders vorteilhaft hat es sich erwiesen, durch Beimischung von Neutronengiften zu der Graphitmasse, vorzugsweise Bor in Form von B4C-Pulver, die Einfangrate für Neutronen zu verbessern. Weiterhin ist es vorteilhaft, die innere Auskleidung 5 mit dem Grundkörper 1 durch Zuganker 11 zu verbinden.It has proven to be particularly advantageous to improve the capture rate for neutrons by adding neutron poisons to the graphite mass, preferably boron in the form of B 4 C powder. Furthermore, it is advantageous to connect the inner lining 5 to the base body 1 by means of tie rods 11.

Die Funktion der inneren Auskleidung 5 kann in speziellen Fällen besonders vorteilhaft von den die Graphitformstücke 9 umkleidenden metallischen Mänteln 10 übernommen werden. Die separate innere Auskleidung 5 kann dann teilweise oder völlig entfallen. Die Graphitformstük- ke 9 sind dann besonders günstig an der Innenseite des Grundkörpers 1 befestigt, beispielsweise durch Führungsschienen 12. Jedoch erfüllen auch andere Befestigungsarten, wie z. B. Schwalbenschwanzführungen 14 im Grundkörper 1 oder Befestigungen, z. B. auf einem Blech 13, den gleichen Zweck.In special cases, 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. However, also perform other types of fastening such. B. dovetail guides 14 in the base body 1 or fastenings, for. B. on a sheet 13, the same purpose.

Die Abschirmschicht 8 kann durch Auswechseln unterschiedlich dicker Graphitformstücke 9 leicht den jeweiligen Erfordernissen angepaßt werden.The shielding layer 8 can be easily adapted to the respective requirements by changing graphite moldings 9 of different thicknesses.

Claims (10)

1. A container for transporting and/or storing radioactive materials, in particular radiation-exposed nuclear fuel elements and high-level radioactive waste, consisting of a basic body having a shielding function with respect to y- and n-radiation and an inner lining of noncorrosive material, characterized in that an n-shielding layer (8), in the form of a material based on graphite, is also positioned between the inner lining (5) and the basic body (1).
2. A container according to claim 1, characterized in that the material consists of a hardening mixture of graphite powder and a binder.
3. A container according to claims 1 and 2, characterized in that the material consists of a hardening mixture of graphite powder and cast resin.
4. A container according to claims 1 to 3, characterized in that the shield consists of shaped pieces of graphite (9).
5. A container according to claim 4, characterized in that the shaped pieces of graphite (9) are enclosed by a metallic sheath (10).
6. A container according to claim 5, characterized in that the metallic sheath (10) is simultaneously the inner lining (5).
7. A container according to claims 4 to 6, characterized in that the shaped pieces of graphite (9) are attached to the inside of the basic body.
8. A container according to claims 1 to 7, characterized in that neutron-absorbing material is also added to the graphite material.
9. A container according to claim 8, characterized in that the neutron-absorbing material which is added to the graphite material is boron carbide powder.
10. A container according to claims 1 to 9, characterized in that the inner lining (5) is attached to the basic body (1) by tie rods (11).
EP81101461A 1980-03-29 1981-02-28 Container for transportation and storage of radioactive substances Expired EP0036954B1 (en)

Applications Claiming Priority (2)

Application Number Priority Date Filing Date Title
DE3012256 1980-03-29
DE19803012256 DE3012256A1 (en) 1980-03-29 1980-03-29 CONTAINER FOR TRANSPORT AND / OR STORAGE OF RADIOACTIVE SUBSTANCES

Publications (2)

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

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EP81101461A Expired EP0036954B1 (en) 1980-03-29 1981-02-28 Container for transportation and storage of radioactive substances

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US (1) US4453081A (en)
EP (1) EP0036954B1 (en)
DE (1) DE3012256A1 (en)
ES (1) ES8305147A1 (en)

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ES8305147A1 (en) 1983-03-16
DE3012256A1 (en) 1981-10-15
US4453081A (en) 1984-06-05
EP0036954A1 (en) 1981-10-07

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