EP0036961B1 - Container for storing tritium - Google Patents

Container for storing tritium Download PDF

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Publication number
EP0036961B1
EP0036961B1 EP81101561A EP81101561A EP0036961B1 EP 0036961 B1 EP0036961 B1 EP 0036961B1 EP 81101561 A EP81101561 A EP 81101561A EP 81101561 A EP81101561 A EP 81101561A EP 0036961 B1 EP0036961 B1 EP 0036961B1
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EP
European Patent Office
Prior art keywords
container
container according
cartridge
filler
tritium
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
EP81101561A
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German (de)
French (fr)
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EP0036961A2 (en
EP0036961A3 (en
Inventor
Josef Knieper
Heinz Printz
Robert Dr. Dipl.-Chem. Wölfle
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Forschungszentrum Juelich GmbH
Original Assignee
Forschungszentrum Juelich GmbH
Kernforschungsanlage Juelich GmbH
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Publication of EP0036961A2 publication Critical patent/EP0036961A2/en
Publication of EP0036961A3 publication Critical patent/EP0036961A3/en
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    • GPHYSICS
    • G21NUCLEAR PHYSICS; NUCLEAR ENGINEERING
    • G21FPROTECTION AGAINST X-RADIATION, GAMMA RADIATION, CORPUSCULAR RADIATION OR PARTICLE BOMBARDMENT; TREATING RADIOACTIVELY CONTAMINATED MATERIAL; DECONTAMINATION ARRANGEMENTS THEREFOR
    • G21F9/00Treating radioactively contaminated material; Decontamination arrangements therefor
    • G21F9/02Treating gases

Definitions

  • the invention relates to a container for storing tritium, which is bound to an adsorbent with molecular sieve properties after prior oxidation to HTO or T 2 0.
  • US-A 3754141 explains how radioactive material is stored in a cartridge which is surrounded by a PVC film.
  • Magnesium oxide is provided as a filler between this film and the outer container. This magnesium oxide is not suitable for the storage of tritium because it cannot prevent diffusion of the tritium and hydrogen.
  • US-A 4031 921 discloses a three-layer pipeline. This is said to be tight against the diffusion of hydrogen and tritium. However, the materials are especially designed so that the pipeline is resistant to temperatures from 300 to 700 ° C.
  • the invention has for its object to provide a container for the storage of tritium, which is completely tight for storage on the one hand, but from which the tritium can be recovered even after prolonged storage.
  • the container consists of a corrosion-resistant metal which is impervious to hydrogen diffusion and at least one cartridge made of pure aluminum is provided in it, in which the adsorbent is enclosed and which is surrounded by a filler made of fire-retardant plastic , a separating layer being provided between the cartridge and the filler.
  • a corrosion-resistant metal which is impervious to hydrogen diffusion
  • the adsorbent is enclosed and which is surrounded by a filler made of fire-retardant plastic , a separating layer being provided between the cartridge and the filler.
  • the molecular sieve contains zeolites which, for the present application, have the highest possible selectivity for water vapor and a high temperature resistance in the loaded state up to over 300 ° C.
  • the container can consist of, for example, pure aluminum, titanium or stainless steel, since these metals are particularly tight against hydrogen diffusion and are also corrosion-resistant.
  • Pure aluminum is particularly characterized because it has a very low permeation rate for HT, high flexibility and thus low risk of breakage, insensitivity to radiolysis, incombustibility and insensitivity to water due to the formation of a coherent oxide layer, which should have a thickness of 50 to 60 ⁇ . This layer can be anodized to a value of 5 to 6 ⁇ m, which results in additional permeation inhibition.
  • the container should be provided with a blind flange or welded for a secure and completely tight seal.
  • the welding is preferably carried out by means of an electron beam in a vacuum.
  • the resulting cavity offers a high level of security against pressure increases in the interior through radiolysis or decomposition gases at high temperatures.
  • the container is coated with glass fiber reinforced plastic, for example polyester, phenol or epoxy resin. This increases the mechanical strength even more and further improves the resistance to aggressive liquids or gases.
  • the molecular sieve should have a cartridge made of pure aluminum as a covering, which is provided with an oxide layer of 50 to 60 ⁇ in thickness and optionally with an anodization.
  • Quick fasteners are used to fill the cartridge in the manner of the known quick connector fasteners. These closures are designed in such a way that they only open automatically if there are suitable connections. Otherwise they are sealed vacuum-tight so that there is no risk of contamination. In addition, they can be opened at any time without risk of contamination, for example to dilute the tritium to a smaller specific final storage activity or to remove it in a controlled manner by passing an inert gas stream through it. When passing the inert gas stream, the amount and concentration of the tritium can be controlled by setting a selected temperature in the range from -190 ° C to + 300 ° C. The withdrawal quantity can be dosed exactly as desired.
  • molecular sieves can also be enclosed in one container. It is then expedient to provide predetermined breaking points in the areas between the molecular sieves so that they can also be removed individually from the container. The remaining molecular sieves are then still covered and can be deposited again.
  • the filler consist of polyester, epoxy or phenolic resin, and / or gypsum and / or cement. These substances, in particular the last three, do not promote or maintain combustion.
  • a separating wax layer should be provided between the molecular sieve and the filler. Due to the softer consistency of the separating wax, the molecular sieve, especially if it is equipped with quick connector closures, is protected from damage when opened later, since the separating wax prevents a direct connection with the filler. Both filler as well Release wax can absorb small amounts of tritium that have stuck to the caps of the cartridge during the process.
  • the multi-layer structure provides optimal protection against external corrosion due to the different chemical vulnerability.
  • a larger number of the device according to the invention can also be introduced into 200 l waste containers, filled with concrete and then transported to final storage, for example in a salt mine.
  • a molecular sieve 1 shows a molecular sieve 1, consisting of a molecular sieve filling 1 a and a cartridge 2 enveloping it made of pure aluminum, the cartridge 2 being provided with quick-release fasteners 3, 4.
  • the cartridge 2 is coated with a release wax layer 5, so that the cartridge 2 does not enter into a connection with the filler 6, in which the molecular sieve 1 is embedded.
  • the outer envelope is formed by a container 7, for example also made of pure aluminum, which is closed with a lid 8. The closure point is sealed with a weld 9.
  • Fig. 2 shows a device for storing tritium, in which three molecular sieves 10, 11, 12 are embedded in cartridge form. These molecular sieves 10, 11, 12 are also each surrounded by a separating wax layer 13 and by a filler 14, for example plastic or gypsum, and by a container 15 made of pure aluminum.
  • the container 15 is additionally coated with a multi-layer, glass fiber reinforced plastic layer 16 and sealed by means of a blind flange with a metal seal 17.
  • the plastic layer 16 seals the container 15 gas and liquid-tight and provides good protection against aggressive liquids or gases.
  • the container 15 can be sawed open for subsequent separation or reopening, the molecular sieves 10, 11, 12 being exposed.
  • predetermined breaking points 18, 19 can be provided on the container 15.
  • the quick fasteners 20 can be connected to a gas or flushing line.
  • the tritium can be dissolved out of the molecular sieves 10, 11, 12 again by passing an inert gas through it.
  • the closures are designed as so-called quick connector closures, which open automatically when the appropriate connections are made and otherwise close absolutely vacuum-tight.

Description

Die Erfindung betrifft einen Behälter zur Lagerung von Tritium, das an einem Adsorbens mit Molekularsiebeigenschaften nach vorheriger Oxidierung zu HTO bzw. T20 gebunden ist.The invention relates to a container for storing tritium, which is bound to an adsorbent with molecular sieve properties after prior oxidation to HTO or T 2 0.

In der US-A 4178 350 ist die Entfernung von Tritium aus einem Gas mittels eines Molekularsiebes beschrieben. Über eine anschliessende Lagerung sagt diese Druckschrift jedoch nichts aus.US-A 4178 350 describes the removal of tritium from a gas by means of a molecular sieve. However, this publication says nothing about subsequent storage.

In der US-A 3754141 ist erläutert, wie radioaktives Material in einer Patrone eingelagert ist, die von einem PVC-Film umgeben ist. Zwischen diesem Film und dem Aussenbehälterist Magnesiumoxid als Füllstoff vorgesehen. Dieses Magnesiumoxid ist für die Einlagerung von Tritium nicht geeignet, da es eine Diffusion des Tritiums und Wasserstoffs nicht verhindern kann.US-A 3754141 explains how radioactive material is stored in a cartridge which is surrounded by a PVC film. Magnesium oxide is provided as a filler between this film and the outer container. This magnesium oxide is not suitable for the storage of tritium because it cannot prevent diffusion of the tritium and hydrogen.

Schliesslich ist in der US-A 4031 921 eine dreischichtig aufgebaute Rohrleitung offenbart. Diese soll zwar gegen die Diffusion von Wasserstoff und Tritium dicht sein. Die Materialien sind jedoch insbesondere daraufhin ausgelegt, dass die Rohrleitung beständig gegen die Temperaturen von 300 bis 700°C ist.Finally, US-A 4031 921 discloses a three-layer pipeline. This is said to be tight against the diffusion of hydrogen and tritium. However, the materials are especially designed so that the pipeline is resistant to temperatures from 300 to 700 ° C.

Der Erfindung liegt die Aufgabe zugrunde, einen Behälter für die Einlagerung von Tritium zu schaffen, der einerseits für die Lagerung vollkommen dicht ist, aus dem das Tritium aber auch nach längerer Lagerung wiedergewonnen werden kann.The invention has for its object to provide a container for the storage of tritium, which is completely tight for storage on the one hand, but from which the tritium can be recovered even after prolonged storage.

Diese Aufgabe wird erfindungsgemäss dadurch gelöst, dass der Behälter aus einem gegen Wasserstoffdiffusion dichten, korrosionsfesten Metall besteht und in ihm zumindest eine mit einem Verschluss versehene Patrone aus Reinaluminium angeordnet ist, in der das Adsorbens eingeschlossen ist und die von einem Füllstoff aus feuerhemmendem Kunststoff umgeben ist, wobei zwischen Patrone und Füllstoff eine Trennschicht vorgesehen ist. Ein solcher Behälter hat sich als absolut dicht gegen die Diffusion von Tritium und Wasserstoff erwiesen, ist also für eine lange Lagerung von Tritium geeignet. Andererseits besteht die Möglichkeit, die Patrone wieder aus dem Behälter herauszulösen und das Tritium dann wiederzugewinnen.This object is achieved according to the invention in that the container consists of a corrosion-resistant metal which is impervious to hydrogen diffusion and at least one cartridge made of pure aluminum is provided in it, in which the adsorbent is enclosed and which is surrounded by a filler made of fire-retardant plastic , a separating layer being provided between the cartridge and the filler. Such a container has proven to be absolutely impermeable to the diffusion of tritium and hydrogen and is therefore suitable for long storage of tritium. On the other hand, there is the possibility of removing the cartridge from the container and then recovering the tritium.

In Ausbildung der Erfindung ist vorgesehen, dass das Molekularsieb Zeolithe enthält, die für den vorliegenden Anwendungszweck eine möglichst hohe Selektivität für Wasserdampf und eine hohe Temperaturbeständigkeit in beladenem Zustand bis über 300°C besitzt.In an embodiment of the invention it is provided that the molecular sieve contains zeolites which, for the present application, have the highest possible selectivity for water vapor and a high temperature resistance in the loaded state up to over 300 ° C.

Der Behälter kann aus beispielsweise Reinaluminium, Titan oder Edelstahl bestehen, da diese Metalle gegen Wasserstoffdiffusion besonders dicht und zudem korrosionsfest sind. Dabei zeichnet sich insbesondere Reinaluminium aus, weil es eine sehr niedrige Permeationsrate für HT, hohe Biegsamkeit und somit niedrige Bruchgefahr, Unempfindlichkeit gegen Radiolyse, Unbrennbarkeit sowie Unempfindlichkeit gegen Wasser infolge Ausbildung einer zusammenhängenden Oxidschicht aufweist, die eine Dicke von 50 bis 60 Ä haben sollte. Diese Schicht kann durch Eloxieren noch auf Werte von 5 bis 6 µm verstärkt werden, wodurch eine zusätzliche Permeationshemmung bewirkt wird.The container can consist of, for example, pure aluminum, titanium or stainless steel, since these metals are particularly tight against hydrogen diffusion and are also corrosion-resistant. Pure aluminum is particularly characterized because it has a very low permeation rate for HT, high flexibility and thus low risk of breakage, insensitivity to radiolysis, incombustibility and insensitivity to water due to the formation of a coherent oxide layer, which should have a thickness of 50 to 60 Å. This layer can be anodized to a value of 5 to 6 µm, which results in additional permeation inhibition.

Zur sicheren und völlig dichten Verschliessung sollte der Behälter mit einem Blindflansch versehen oder zugeschweisst sein. Die Verschweissung erfolgt vorzugsweise durch Elektronenstrahl im Vakuum. Der dabei entstandene Hohlraum bietet eine hohe Sicherheit vor Druckanstieg im Innenraum durch Radiolyse oder Zersetzungsgase bei hohen Temperaturen.The container should be provided with a blind flange or welded for a secure and completely tight seal. The welding is preferably carried out by means of an electron beam in a vacuum. The resulting cavity offers a high level of security against pressure increases in the interior through radiolysis or decomposition gases at high temperatures.

Als zusätzliche Sicherungsmassnahme kann vorgesehen sein, dass der Behälter mit glasfaserverstärktem Kunststoff, beispielsweise Polyester-, Phenol- oder Epoxidharz, ummantelt wird. Hierdurch wird die mechanische Festigkeit noch mehr erhöht und die Beständigkeit gegen aggressive Flüssigkeiten oder Gase weiter verbessert.As an additional security measure it can be provided that the container is coated with glass fiber reinforced plastic, for example polyester, phenol or epoxy resin. This increases the mechanical strength even more and further improves the resistance to aggressive liquids or gases.

Das Molekularsieb sollte eine Patrone aus Reinaluminium als Umhüllung haben, die mit einer Oxidschicht von 50 bis 60 Ä Dicke und gegebenenfalls mit einer Eloxierung versehen ist.The molecular sieve should have a cartridge made of pure aluminum as a covering, which is provided with an oxide layer of 50 to 60 Å in thickness and optionally with an anodization.

Zur Befüllung der Patrone dienen Schnellverschlüsse nach Art der bekannten Quickconnectorverschlüsse. Diese Verschlüsse sind so ausgebildet, dass sie sich nur dann automatisch öffnen, wenn dazu passende Anschlüsse angebracht sind. Ansonsten sind sie vakuumdicht verschlossen, so dass keine Kontaminationsgefahr besteht. Ausserdem lassen sie sich jederzeit ohne Kontaminationsgefahr öffnen, beispielsweise um das Tritium auf eine kleinere spezifische Endlagerungsaktivität zu verdünnen oder mittels Durchleiten eines Inertgasstromes kontrolliert zu entnehmen. Beim Durchleiten des Inertgasstromes können Menge und Konzentration des Tritiums mittels Einstellung einer gewählten Temperatur im Bereich von -190°C bis +300°C gesteuert werden. Dabei kann die Entnahmemenge je nach Wunsch genau dosiert werden.Quick fasteners are used to fill the cartridge in the manner of the known quick connector fasteners. These closures are designed in such a way that they only open automatically if there are suitable connections. Otherwise they are sealed vacuum-tight so that there is no risk of contamination. In addition, they can be opened at any time without risk of contamination, for example to dilute the tritium to a smaller specific final storage activity or to remove it in a controlled manner by passing an inert gas stream through it. When passing the inert gas stream, the amount and concentration of the tritium can be controlled by setting a selected temperature in the range from -190 ° C to + 300 ° C. The withdrawal quantity can be dosed exactly as desired.

Es besteht die Möglichkeit, dass in einem Behälter auch mehrere Molekularsiebe eingeschlossen werden. Dann ist es zweckmässig, Sollbruchstellen in den Bereichen zwischen den Molekularsieben vorzusehen, damit sie auch einzeln aus dem Behälter entnommen werden können. Die verbleibenden Molekularsiebe sind dann weiterhin ummantelt und können wieder abgelagert werden.It is possible that several molecular sieves can also be enclosed in one container. It is then expedient to provide predetermined breaking points in the areas between the molecular sieves so that they can also be removed individually from the container. The remaining molecular sieves are then still covered and can be deposited again.

Nach einem weiteren Merkmal der Erfindung ist vorgeschlagen, dass der Füllstoff aus Polyester-, Epoxid- oder Phenolharz, und/oder Gips und/oder Zement besteht. Diese Stoffe, insbesondere die drei letztgenannten, fördern oder unterhalten die Verbrennung nicht.According to a further feature of the invention, it is proposed that the filler consist of polyester, epoxy or phenolic resin, and / or gypsum and / or cement. These substances, in particular the last three, do not promote or maintain combustion.

Zusätzlich sollte zwischen dem Molekularsieb und dem Füllstoff eine Trennwachsschicht vorgesehen werden. Durch die weichere Konsistenz des Trennwachses wird das Molekularsieb, insbesondere wenn es mit Quickconnectorverschlüssen versehen ist, bei einer späteren Öffnung vor Beschädigungen geschützt, da der Trennwachs eine direkte Verbindung mit dem Füllstoff verhindert. Sowohl Füllstoff als auch Trennwachs können kleinere Tritiummengen aufnehmen, die an den Verschlüssen der Patrone während des Vorganges haften geblieben sind. Der Mehrschichtenaufbau bildet wegen der verschiedenartigen chemischen Angreifbarkeit einen optimalen Schutz vor äusserer Korrosion.In addition, a separating wax layer should be provided between the molecular sieve and the filler. Due to the softer consistency of the separating wax, the molecular sieve, especially if it is equipped with quick connector closures, is protected from damage when opened later, since the separating wax prevents a direct connection with the filler. Both filler as well Release wax can absorb small amounts of tritium that have stuck to the caps of the cartridge during the process. The multi-layer structure provides optimal protection against external corrosion due to the different chemical vulnerability.

Es können auch eine grössere Anzahl von der erfindungsgemässen Vorrichtung in 200-I-Abfallbehälter eingebracht, mit Beton verfüllt und dann zur Endlagerung, beispielsweise in ein Salzbergwerk, transportiert werden.A larger number of the device according to the invention can also be introduced into 200 l waste containers, filled with concrete and then transported to final storage, for example in a salt mine.

In der Zeichnung ist die Erfindung anhand von Ausführungsbeispielen näher veranschaulicht.In the drawing, the invention is illustrated in more detail using exemplary embodiments.

Es zeigen:

  • Fig. 1 eine Vorrichtung zur Lagerung von Tritium mit einem Molekularsieb im Längsschnitt und
  • Fig. 2 eine Vorrichtung mit drei Molekularsieben im Längsschnitt.
Show it:
  • Fig. 1 shows a device for storing tritium with a molecular sieve in longitudinal section and
  • Fig. 2 shows a device with three molecular sieves in longitudinal section.

Fig. 1 zeigt ein Molekularsieb 1, bestehend aus einer Molekularsiebfüllung 1a und einer diese umhüllenden Patrone 2 aus Reinaluminium, wobei die Patrone 2 mit Schnellverschlüssen 3, 4 versehen ist. Die Patrone 2 ist mit einer Trennwachsschicht 5 umhüllt, damit die Patrone 2 keine Verbindung mit dem Füllstoff 6 eingeht, in den das Molekularsieb 1 eingelagert ist. Die äussere Umhüllung wird durch einen Behälter 7, beispielsweise ebenfalls aus Reinaluminium, gebildet, der mit einem Deckel 8 verschlossen ist. Die Verschlussstelle ist mit einer Schweissnaht 9 abgedichtet.1 shows a molecular sieve 1, consisting of a molecular sieve filling 1 a and a cartridge 2 enveloping it made of pure aluminum, the cartridge 2 being provided with quick-release fasteners 3, 4. The cartridge 2 is coated with a release wax layer 5, so that the cartridge 2 does not enter into a connection with the filler 6, in which the molecular sieve 1 is embedded. The outer envelope is formed by a container 7, for example also made of pure aluminum, which is closed with a lid 8. The closure point is sealed with a weld 9.

Fig. 2 zeigt eine Vorrichtung zur Lagerung von Tritium, in die drei Molekularsiebe 10, 11, 12 in Patronenform eingebettet sind. Auch diese Molekularsiebe 10, 11, 12 sind jeweils von einer Trennwachsschicht 13 und von einem Füllstoff 14, beispielsweise Kunststoff oder Gips, sowie von einem Behälter 15 aus Reinaluminium umschlossen. Der Behälter 15 ist zusätzlich noch mit einer mehrlagigen, glasfaserverstärkten Kunststoffschicht 16 ummantelt und mittels eines Blindflansches mit einer Metalldichtung 17 abgedichtet. Die Kunststoffschicht 16 schliesst den Behälter 15 gas- und flüssigkeitsdicht ab und bildet einen guten Schutz gegen aggressive Flüssigkeiten oder Gase.Fig. 2 shows a device for storing tritium, in which three molecular sieves 10, 11, 12 are embedded in cartridge form. These molecular sieves 10, 11, 12 are also each surrounded by a separating wax layer 13 and by a filler 14, for example plastic or gypsum, and by a container 15 made of pure aluminum. The container 15 is additionally coated with a multi-layer, glass fiber reinforced plastic layer 16 and sealed by means of a blind flange with a metal seal 17. The plastic layer 16 seals the container 15 gas and liquid-tight and provides good protection against aggressive liquids or gases.

Zur nachträglichen Trennung bzw. Wiederöffnung kann der Behälter 15 aufgesägt werden, wobei die Molekularsiebe 10, 11, 12 freigelegt werden. Zur Erleichterung des Auftrennens können Sollbruchstellen 18, 19 am Behälter 15 vorgesehen werden.The container 15 can be sawed open for subsequent separation or reopening, the molecular sieves 10, 11, 12 being exposed. To facilitate separation, predetermined breaking points 18, 19 can be provided on the container 15.

Sobald die Molekularsiebe 10, 11, 12 freigelegt sind, können die Schnellverschlüsse 20 an eine Gas- oder Spülleitung angeschlossen werden. Mittels Hindurchleiten eines Inertgases kann das Tritium wieder aus den Molekularsieben 10, 11, 12 herausgelöst werden. Die Verschlüsse sind dabei als sogenannte Quickconnectorverschlüsse ausgebildet, die sich automatisch öffnen, wenn die dazu passenden Anschlüsse angebracht werden und ansonsten absolut vakuumdicht schliessen.As soon as the molecular sieves 10, 11, 12 are exposed, the quick fasteners 20 can be connected to a gas or flushing line. The tritium can be dissolved out of the molecular sieves 10, 11, 12 again by passing an inert gas through it. The closures are designed as so-called quick connector closures, which open automatically when the appropriate connections are made and otherwise close absolutely vacuum-tight.

Claims (12)

1. Container for storing tritium which is combined with an adsorbent having molecular sieve properties after previous oxidation to form HTO or T20, characterised in that the container (7, 15) is made of a metal resistant to corrosion and sealing-tight against hydrogen diffusion, and in the container there is arranged at least one cartridge (2) of pure aluminium which is provided with a closure and which contains the adsorbent and which is surrounded by a filler (6,14) of fire-inhibiting synthetic plastic material, a separating layer (5, 13) being provided between the cartridge (2) and tile filler (6, 14).
2. Container according to claim 1, characterised in that the molecular sieve (1, 10, 11, 12) has high selectivity for water vapour and a high temperature stability in the charged state to over 300°C.
3. Container according to claim 1 or 2, characterised in that the container (7, 15) is made of pure aluminium or special steel.
4. Container according to claim 3, characterised in that the container (7,15) made of pure aluminium is provided with an oxide layer of 50 to 60 A, possibly reinforced by a treatment by the Eloxal process.
5. Container according to one of claims 1 to 4, characterised in that the container is closed by welding or is provided with a blind flange.
6. Container according to one of claims 4 to 8, characterised in that the container (15) is covered with glass-fibre-reinforced synthetic plastic material, for example polyester resin, phenolic resin or epoxy resin.
7. Container according to one of claims 1 to 6, characterised in that the cartridge (2) has an oxide layer of 50 to 60 A thickness, possibly reinforced by a treatment by the Eloxal process.
8. Container according to one of claims 1 to 7, characterised in that the cartridge (2) comprises rapid-action closures of the quick-connector closure type.
9. Container according to one of claims 1 to 8, characterised in that a plurality of molecular sieves (10, 11, 12) are enclosed in a container (15).
10. Container according to claim 9, characterised in that the container (15) comprises predetermined breaking points (18, 19) in the regions between the molecular sieves (10, 11, 12).
11. Container according to one of claims 1 to 10, characterised in that the filler (6, 14) consists of polyester resin, phenolic resin or epoxy resin.
12. Container according to one of claims 1 to 11, characterised in that the separating layer is in the form of a wax layer.
EP81101561A 1980-03-26 1981-03-05 Container for storing tritium Expired EP0036961B1 (en)

Applications Claiming Priority (2)

Application Number Priority Date Filing Date Title
DE19803011602 DE3011602A1 (en) 1980-03-26 1980-03-26 METHOD AND DEVICE FOR THE FINAL STORAGE OF TRITIUM, ESPECIALLY TRITIUM WASTE FROM NUCLEAR POWER PLANTS, WITH THE POSSIBILITY OF TRITIUM RECOVERY
DE3011602 1980-03-26

Publications (3)

Publication Number Publication Date
EP0036961A2 EP0036961A2 (en) 1981-10-07
EP0036961A3 EP0036961A3 (en) 1982-01-13
EP0036961B1 true EP0036961B1 (en) 1985-06-12

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EP81101561A Expired EP0036961B1 (en) 1980-03-26 1981-03-05 Container for storing tritium

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US (1) US4424903A (en)
EP (1) EP0036961B1 (en)
JP (1) JPS5712399A (en)
CA (1) CA1148671A (en)
DE (2) DE3011602A1 (en)

Families Citing this family (24)

* Cited by examiner, † Cited by third party
Publication number Priority date Publication date Assignee Title
DE3142646C2 (en) * 1981-10-28 1985-10-17 Deutsche Gesellschaft für Wiederaufarbeitung von Kernbrennstoffen mbH, 3000 Hannover Fuel element container for transporting and / or storing nuclear reactor fuel elements
JPS5985999A (en) * 1982-11-08 1984-05-18 秩父セメント株式会社 Multiple container and its manufacture
DE3310041A1 (en) * 1983-03-19 1984-09-20 Kernforschungszentrum Karlsruhe Gmbh, 7500 Karlsruhe METHOD FOR DETERMINING THE (ARROW HIGH) 3 (ARROW HIGH) H CONCENTRATION OF HUMIDITY
DE3330460A1 (en) * 1983-08-24 1985-03-07 Kernforschungszentrum Karlsruhe Gmbh, 7500 Karlsruhe METHOD FOR FIXING RADIOACTIVE, GASEOUS COMPONENTS OF EXHAUST GAS
FR2583208B1 (en) * 1985-06-07 1992-04-24 Commissariat Energie Atomique PROCESS AND DEVICE FOR THE TREATMENT OF NON-ORGANIC SOLID TRITY WASTE
DE3525772C1 (en) * 1985-07-19 1986-09-04 Gkss - Forschungszentrum Geesthacht Gmbh, 2054 Geesthacht Process for conditioning tritium to make it ready for final storage
DE3642975C1 (en) * 1986-12-17 1988-02-11 Wiederaufarbeitung Von Kernbre Process for the production of a solid product suitable for final storage of tritium-containing waste water
DE3726770C2 (en) * 1987-08-12 1993-11-11 Ieg Ind Engineering Gmbh Filter device for filtering out volatile impurities from an air stream
FR2620262B1 (en) * 1987-09-09 1989-11-17 Commissariat Energie Atomique PROCESS AND PLANT FOR THE TREATMENT OF SOLID ORGANIC WASTE CONTAMINATED WITH TRITIUM
US4950426A (en) * 1989-03-31 1990-08-21 Westinghouse Electric Corp. Granular fill material for nuclear waste containing modules
JP2547453B2 (en) * 1989-09-28 1996-10-23 動力灯・核燃料開発事業団 Volume reduction method for radioactive metal waste
GB9017038D0 (en) * 1990-08-03 1990-09-19 Alcan Int Ltd Controlled hydrogen generation from composite powder material
US5464988A (en) * 1994-11-23 1995-11-07 The United States Of America As Represented By The Department Of Energy Tritium waste package
US6348153B1 (en) 1998-03-25 2002-02-19 James A. Patterson Method for separating heavy isotopes of hydrogen oxide from water
FR2859042B1 (en) * 2003-08-19 2005-11-18 Framatome Anp PROCESS AND PLANT FOR PROCESSING ALKALINE METALS CHARGED WITH TRITIUM OR COMPONENTS SUBJECTED BY ALKALINE METALS CHARGED WITH TRITIUM
US6984327B1 (en) 2004-11-23 2006-01-10 Patterson James A System and method for separating heavy isotopes of hydrogen oxide from water
DE102011085480A1 (en) * 2011-10-28 2013-05-02 Volkmar Gräf CONTAINER SYSTEM FOR THE END STORAGE OF RADIOACTIVE WASTE AND / OR POISONOIL
FR2984003B1 (en) * 2011-12-12 2014-01-10 Commissariat Energie Atomique METHOD AND DEVICE FOR REDUCING THE DEGASSING OF TRIUCED WASTE FROM THE NUCLEAR INDUSTRY
CN105976871B (en) * 2016-06-06 2017-07-18 中国工程物理研究院核物理与化学研究所 A kind of processing method of fusion-fission hybrid reactor fusion target chamber product
CN105976884B (en) * 2016-06-29 2017-11-07 中国工程物理研究院材料研究所 The processing unit and processing method of a kind of tritium-containing liquid waste
US9827063B1 (en) * 2016-07-06 2017-11-28 Medtronic Vascular, Inc. Hybrid sealed tray for long catheter delivery systems
CN106297932B (en) * 2016-08-30 2017-11-10 中国工程物理研究院材料研究所 A kind of tritium-containing liquid waste processing system and processing method
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FR3126148A1 (en) * 2021-08-11 2023-02-17 Max Sardou LINER that is to say: internal envelope of COMPOSITE TANK for HIGH PRESSURE GAS

Citations (8)

* Cited by examiner, † Cited by third party
Publication number Priority date Publication date Assignee Title
US3432666A (en) * 1964-03-13 1969-03-11 Atomic Energy Authority Uk Containers for transporting radioactive and/or fissile materials
US3754141A (en) * 1972-07-12 1973-08-21 Atomic Energy Commission Shipping and storage container for high power density radioactive materials
JPS5073098A (en) * 1973-11-02 1975-06-17
US3935467A (en) * 1973-11-09 1976-01-27 Nuclear Engineering Co., Inc. Repository for fissile materials
DE2741661A1 (en) * 1977-09-16 1979-03-22 Strahlen Umweltforsch Gmbh PROCEDURE FOR COVERING WASTE BAGS WITH A LEAK-PROOF, CLOSED CASE
US4158639A (en) * 1977-11-14 1979-06-19 Autoclave Engineers, Inc. Method of storing gases
JPS54120400A (en) * 1978-03-10 1979-09-18 Kobe Steel Ltd Sealing method of radioactive waste gas by zeolite
US4315831A (en) * 1976-08-13 1982-02-16 Commissariat A L'energie Atomique Process for the conditioning of solid radioactive waste with large dimensions

Family Cites Families (3)

* Cited by examiner, † Cited by third party
Publication number Priority date Publication date Assignee Title
DE2138241A1 (en) * 1971-07-30 1973-02-08 Nukem Gmbh PROCESS FOR BINDING RESIDUAL GASES FROM NUCLEAR SYSTEMS, IN PARTICULAR FOR THE REMOVAL OF HYDROGEN GAS FROM AIR
US4178350A (en) * 1973-08-27 1979-12-11 Engelhard Minerals & Chemicals Corp. Removal of tritium and tritium-containing compounds from a gaseous stream
US4031921A (en) * 1975-09-09 1977-06-28 The United States Of America As Represented By The United States Energy Research And Development Administration Hydrogen-isotope permeation barrier

Patent Citations (8)

* Cited by examiner, † Cited by third party
Publication number Priority date Publication date Assignee Title
US3432666A (en) * 1964-03-13 1969-03-11 Atomic Energy Authority Uk Containers for transporting radioactive and/or fissile materials
US3754141A (en) * 1972-07-12 1973-08-21 Atomic Energy Commission Shipping and storage container for high power density radioactive materials
JPS5073098A (en) * 1973-11-02 1975-06-17
US3935467A (en) * 1973-11-09 1976-01-27 Nuclear Engineering Co., Inc. Repository for fissile materials
US4315831A (en) * 1976-08-13 1982-02-16 Commissariat A L'energie Atomique Process for the conditioning of solid radioactive waste with large dimensions
DE2741661A1 (en) * 1977-09-16 1979-03-22 Strahlen Umweltforsch Gmbh PROCEDURE FOR COVERING WASTE BAGS WITH A LEAK-PROOF, CLOSED CASE
US4158639A (en) * 1977-11-14 1979-06-19 Autoclave Engineers, Inc. Method of storing gases
JPS54120400A (en) * 1978-03-10 1979-09-18 Kobe Steel Ltd Sealing method of radioactive waste gas by zeolite

Also Published As

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EP0036961A2 (en) 1981-10-07
CA1148671A (en) 1983-06-21
DE3170920D1 (en) 1985-07-18
US4424903A (en) 1984-01-10
EP0036961A3 (en) 1982-01-13
JPS5712399A (en) 1982-01-22
DE3011602A1 (en) 1981-10-08

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