EP0036961A2 - Récipient pour le stockage du tritium - Google Patents

Récipient pour le stockage du tritium Download PDF

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Publication number
EP0036961A2
EP0036961A2 EP81101561A EP81101561A EP0036961A2 EP 0036961 A2 EP0036961 A2 EP 0036961A2 EP 81101561 A EP81101561 A EP 81101561A EP 81101561 A EP81101561 A EP 81101561A EP 0036961 A2 EP0036961 A2 EP 0036961A2
Authority
EP
European Patent Office
Prior art keywords
tritium
container
molecular sieve
cartridge
filler
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
EP81101561A
Other languages
German (de)
English (en)
Other versions
EP0036961B1 (fr
EP0036961A3 (en
Inventor
Josef Knieper
Heinz Printz
Robert Dr. Dipl.-Chem. Wölfle
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.)
Forschungszentrum Juelich GmbH
Original Assignee
Forschungszentrum Juelich GmbH
Kernforschungsanlage Juelich 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 Forschungszentrum Juelich GmbH, Kernforschungsanlage Juelich GmbH filed Critical Forschungszentrum Juelich GmbH
Publication of EP0036961A2 publication Critical patent/EP0036961A2/fr
Publication of EP0036961A3 publication Critical patent/EP0036961A3/de
Application granted granted Critical
Publication of EP0036961B1 publication Critical patent/EP0036961B1/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
    • G21F9/00—Treating radioactively contaminated material; Decontamination arrangements therefor
    • G21F9/02—Treating gases

Definitions

  • the invention relates to a method for storing tritium, in particular tritium waste from nuclear power plants, and to a device for carrying out this method.
  • Tritium has so far been poured into concrete for final storage. Due to the properties of the concrete, this is only permitted in quantities of up to 10 millicuries. The removal of larger amounts of tritium is therefore very complex. In addition, the tritium is not recoverable afterwards. This can become important when the fusion reactor technology is more advanced because it requires tritium.
  • the invention is therefore based on the object of finding a method with which tritium or tritium-containing substances can be stored safely and without problems and can be recovered at any time.
  • the tritium is oxidized to HTO or T 2 O, bound to an adsorbent with molecular sieve properties and the adsorbent is then surrounded by a corrosion-resistant metal container which is sealed against hydrogen diffusion. Larger amounts of tritium can also be stored relatively safely using this method. It is particularly advantageous that the tritium can be easily recovered.
  • the tritium can be oxidized, for example, by oxidation of HT or tritiated organic compounds on heated copper oxide.
  • the oxidized tritium can be easily bound to the adsorbent under dry inert gas. Dry air, nitrogen or argon can be used as inert gases. The inert gas can also be used in the same way for the recovery of the tritium.
  • the device for storing tritium according to the invention is characterized by a container consisting of a metal which is impermeable to hydrogen diffusion, in which a molecular sieve, loaded with tritium in the form of HTO or T 2 O and encased by a filler, is enclosed.
  • a molecular sieve contains zeolites which, for the present application, should have the highest possible selectivity for water vapor and a high temperature resistance in the loaded state up to over 3oo 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 stands out in particular because it has a very low permeation rate for HT, high flexibility and thus low risk of breakage, insensitivity to radiolysis; Has incombustibility and insensitivity to water due to the formation of a coherent oxide layer, which should have a thickness of 5o to 6 0 A. This layer can be anodized to a value of 5 to 6 ⁇ m, which causes an 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 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, or with material of the type that is used in the manufacture of heat shields on space capsules.
  • glass fiber reinforced plastic for example polyester, phenol or epoxy resin
  • material of the type that is used in the manufacture of heat shields on space capsules is coated with glass fiber reinforced plastic, for example polyester, phenol or epoxy resin, or with material of the type that is used in the manufacture of heat shields on space capsules.
  • the molecular sieve should have a pure aluminum patron.
  • the cartridge having an oxide layer of 5o to 6 0 thickness may be optionally provided with an anodizing.
  • 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 suitable connections are fitted. Otherwise they are sealed vacuum-tight so that there is no risk of contamination. They can also 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 tritium can be controlled by setting a selected temperature in the range from -19o ° C to + 3oo ° C. The withdrawal quantity can be dosed exactly as desired.
  • the filler be made of plastic, for example Po there is 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 separation 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 provided with quick connector closures, is protected from damage when opened later, since the separating wax prevents a direct connection with the filler. Both filler and 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 2oo 1 waste containers, filled with concrete and then transported to final storage, for example in a salt mine.
  • Fig. 1 shows a molecular sieve 1, consisting of a molecular sieve filling la and a cartridge 2 enveloping it made of pure aluminum, the cartridge 2 with Schnell closures 3, 4 is provided.
  • 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 is embedded.
  • the outer casing 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 lo, 11, 12 are embedded in cartridge form. These molecular sieves 10, 11, 12 are also each surrounded by a release 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 closes the container 15 in a gas-tight and liquid-tight manner and forms 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-release fasteners lo can be connected to a gas or flushing line.
  • the tritium can be dissolved out again from the molecular sieves 10, 11, 12 by passing an inert gas through it.
  • the closures are designed as so-called quick connector closures that open automatically when the appropriate ones are used Connections are attached and otherwise close absolutely vacuum-tight.

Landscapes

  • Physics & Mathematics (AREA)
  • Engineering & Computer Science (AREA)
  • General Engineering & Computer Science (AREA)
  • High Energy & Nuclear Physics (AREA)
  • Filling Or Discharging Of Gas Storage Vessels (AREA)
  • Solid-Sorbent Or Filter-Aiding Compositions (AREA)
EP81101561A 1980-03-26 1981-03-05 Récipient pour le stockage du tritium Expired EP0036961B1 (fr)

Applications Claiming Priority (2)

Application Number Priority Date Filing Date Title
DE3011602 1980-03-26
DE19803011602 DE3011602A1 (de) 1980-03-26 1980-03-26 Verfahren und vorrichtung zur endlagerung von tritium, insbesondere tritiumabfaellen aus kernkraftwerken, mit der moeglichkeit der tritiumrueckgewinnung

Publications (3)

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

Family

ID=6098336

Family Applications (1)

Application Number Title Priority Date Filing Date
EP81101561A Expired EP0036961B1 (fr) 1980-03-26 1981-03-05 Récipient pour le stockage du tritium

Country Status (5)

Country Link
US (1) US4424903A (fr)
EP (1) EP0036961B1 (fr)
JP (1) JPS5712399A (fr)
CA (1) CA1148671A (fr)
DE (2) DE3011602A1 (fr)

Cited By (6)

* Cited by examiner, † Cited by third party
Publication number Priority date Publication date Assignee Title
EP0119512A3 (en) * 1983-03-19 1985-07-31 Kernforschungszentrum Karlsruhe Gmbh Method of determining the tritium concentration of humid air
US4567014A (en) * 1981-10-28 1986-01-28 Deutsche Gesellschaft Fur Wiederaufarbeitung Von Kernbrennstoffen Mbh Container for transporting and storing nuclear reactor fuel elements
EP0139955A3 (en) * 1983-08-24 1986-05-28 Kernforschungszentrum Karlsruhe Gmbh Process for determining gaseaos radioactive components from exhaust gases
US4594513A (en) * 1982-11-08 1986-06-10 Chichibu Cement Co., Ltd. Multiplex design container having a three-layered wall structure and a process for producing the same
EP0204634A1 (fr) * 1985-06-07 1986-12-10 Commissariat A L'energie Atomique Procédé et dispositif pour le traitement de déchets tritiés solides non organiques
WO2013060326A1 (fr) * 2011-10-28 2013-05-02 Graef Volkmar Système de conteneurs pour le stockage intermédiaire ou définitif de déchets radioactifs et/ou toxiques

Families Citing this family (18)

* Cited by examiner, † Cited by third party
Publication number Priority date Publication date Assignee Title
DE3525772C1 (de) * 1985-07-19 1986-09-04 Gkss - Forschungszentrum Geesthacht Gmbh, 2054 Geesthacht Verfahren zur endlagerreifen Konditionierung von Tritium
DE3642975C1 (de) * 1986-12-17 1988-02-11 Wiederaufarbeitung Von Kernbre Verfahren zur Herstellung eines zur Endlagerung tritiumhaltiger Abwaesser geeigneten Festprodukts
DE3726770C2 (de) * 1987-08-12 1993-11-11 Ieg Ind Engineering Gmbh Filtereinrichtung zum Ausfiltern leichtflüchtiger Verunreinigungen aus einem Luftstrom
FR2620262B1 (fr) * 1987-09-09 1989-11-17 Commissariat Energie Atomique Procede et installation de traitement de dechets organiques solides contamines par du tritium
US4950426A (en) * 1989-03-31 1990-08-21 Westinghouse Electric Corp. Granular fill material for nuclear waste containing modules
JP2547453B2 (ja) * 1989-09-28 1996-10-23 動力灯・核燃料開発事業団 放射性金属廃棄物の減容処理方法
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 (fr) * 2003-08-19 2005-11-18 Framatome Anp Procede et installation de traitement de metaux alcalins charges en tritium ou de composants souilles par des metaux alcalins charges en tritium
US6984327B1 (en) 2004-11-23 2006-01-10 Patterson James A System and method for separating heavy isotopes of hydrogen oxide from water
FR2984003B1 (fr) * 2011-12-12 2014-01-10 Commissariat Energie Atomique Procede et dispositif de reduction du degazage de dechets trities issus de l'industrie nucleaire
CN105976871B (zh) * 2016-06-06 2017-07-18 中国工程物理研究院核物理与化学研究所 一种聚变‑裂变混合堆聚变靶室产物的处理方法
CN105976884B (zh) * 2016-06-29 2017-11-07 中国工程物理研究院材料研究所 一种含氚废水的处理装置及处理方法
US9827063B1 (en) * 2016-07-06 2017-11-28 Medtronic Vascular, Inc. Hybrid sealed tray for long catheter delivery systems
CN106297932B (zh) * 2016-08-30 2017-11-10 中国工程物理研究院材料研究所 一种含氚废水处理系统及处理方法
CN109637688B (zh) * 2018-12-25 2024-09-06 中国原子能科学研究院 一种防氚渗透的放射性固体废物储存桶
FR3126148B1 (fr) * 2021-08-11 2025-11-28 Max Sardou LINER c’est-à-dire:enveloppeinterne deRESERVOIRCOMPOSITEpour GAZà HAUTE PRESSION

Family Cites Families (11)

* Cited by examiner, † Cited by third party
Publication number Priority date Publication date Assignee Title
GB1073751A (en) * 1964-03-13 1967-06-28 Atomic Energy Authority Uk Improvements in or relating to containers for transporting radioactive and/or fissile materials
DE2138241A1 (de) * 1971-07-30 1973-02-08 Nukem Gmbh Verfahren zur bindung von restgasen von kerntechnischen anlagen, insbesondere zur entfernung von wasserstoffgas aus luft
US3754141A (en) * 1972-07-12 1973-08-21 Atomic Energy Commission Shipping and storage container for high power density radioactive materials
US4178350A (en) * 1973-08-27 1979-12-11 Engelhard Minerals & Chemicals Corp. Removal of tritium and tritium-containing compounds from a gaseous stream
JPS5852199B2 (ja) * 1973-11-02 1983-11-21 株式会社日立製作所 ホウシヤセイトリチウムカイシユウコテイホウ
US3935467A (en) * 1973-11-09 1976-01-27 Nuclear Engineering Co., Inc. Repository for fissile materials
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
FR2361725A1 (fr) * 1976-08-13 1978-03-10 Commissariat Energie Atomique Procede de stockage de dechets radioactifs solides de grandes dimensions
DE2741661C2 (de) * 1977-09-16 1986-12-11 Gesellschaft für Strahlen- und Umweltforschung mbH, 8000 München Verfahren zur Umkleidung von Abfallfässern mit einer auslaugsicheren, geschlossenen Hülle
US4158639A (en) * 1977-11-14 1979-06-19 Autoclave Engineers, Inc. Method of storing gases
JPS5910518B2 (ja) * 1978-03-10 1984-03-09 株式会社神戸製鋼所 放射性気体廃棄物のゼオライトによる封入方法

Cited By (7)

* Cited by examiner, † Cited by third party
Publication number Priority date Publication date Assignee Title
US4567014A (en) * 1981-10-28 1986-01-28 Deutsche Gesellschaft Fur Wiederaufarbeitung Von Kernbrennstoffen Mbh Container for transporting and storing nuclear reactor fuel elements
US4594513A (en) * 1982-11-08 1986-06-10 Chichibu Cement Co., Ltd. Multiplex design container having a three-layered wall structure and a process for producing the same
EP0119512A3 (en) * 1983-03-19 1985-07-31 Kernforschungszentrum Karlsruhe Gmbh Method of determining the tritium concentration of humid air
EP0139955A3 (en) * 1983-08-24 1986-05-28 Kernforschungszentrum Karlsruhe Gmbh Process for determining gaseaos radioactive components from exhaust gases
EP0204634A1 (fr) * 1985-06-07 1986-12-10 Commissariat A L'energie Atomique Procédé et dispositif pour le traitement de déchets tritiés solides non organiques
FR2583208A1 (fr) * 1985-06-07 1986-12-12 Commissariat Energie Atomique Procede et dispositif pour le traitement de dechets trities solides non organiques
WO2013060326A1 (fr) * 2011-10-28 2013-05-02 Graef Volkmar Système de conteneurs pour le stockage intermédiaire ou définitif de déchets radioactifs et/ou toxiques

Also Published As

Publication number Publication date
DE3170920D1 (en) 1985-07-18
JPS5712399A (en) 1982-01-22
CA1148671A (fr) 1983-06-21
US4424903A (en) 1984-01-10
DE3011602A1 (de) 1981-10-08
EP0036961B1 (fr) 1985-06-12
EP0036961A3 (en) 1982-01-13

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