DE1082993B - Procedure for disposal of radioactive liquid - Google Patents
Procedure for disposal of radioactive liquidInfo
- Publication number
- DE1082993B DE1082993B DEA31154A DEA0031154A DE1082993B DE 1082993 B DE1082993 B DE 1082993B DE A31154 A DEA31154 A DE A31154A DE A0031154 A DEA0031154 A DE A0031154A DE 1082993 B DE1082993 B DE 1082993B
- Authority
- DE
- Germany
- Prior art keywords
- isodisperse
- liquid
- radiation
- grain mixture
- mixture
- 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.)
- Pending
Links
- 239000007788 liquid Substances 0.000 title claims description 18
- 238000000034 method Methods 0.000 title claims description 11
- 230000002285 radioactive effect Effects 0.000 title claims description 5
- 239000000463 material Substances 0.000 claims description 20
- 239000011230 binding agent Substances 0.000 claims description 11
- 239000000203 mixture Substances 0.000 claims description 11
- 230000005855 radiation Effects 0.000 claims description 10
- 239000004568 cement Substances 0.000 claims description 8
- 230000002745 absorbent Effects 0.000 claims description 5
- 239000002250 absorbent Substances 0.000 claims description 5
- TZCXTZWJZNENPQ-UHFFFAOYSA-L barium sulfate Chemical compound [Ba+2].[O-]S([O-])(=O)=O TZCXTZWJZNENPQ-UHFFFAOYSA-L 0.000 claims description 5
- 239000010428 baryte Substances 0.000 claims description 5
- 229910052601 baryte Inorganic materials 0.000 claims description 5
- 238000010521 absorption reaction Methods 0.000 claims description 3
- 238000005266 casting Methods 0.000 claims description 3
- 229920005989 resin Polymers 0.000 claims description 3
- 239000011347 resin Substances 0.000 claims description 3
- PNEYBMLMFCGWSK-UHFFFAOYSA-N aluminium oxide Inorganic materials [O-2].[O-2].[O-2].[Al+3].[Al+3] PNEYBMLMFCGWSK-UHFFFAOYSA-N 0.000 claims description 2
- 229910052500 inorganic mineral Inorganic materials 0.000 claims description 2
- 239000011707 mineral Substances 0.000 claims description 2
- 230000004048 modification Effects 0.000 claims description 2
- 238000012986 modification Methods 0.000 claims description 2
- 239000002699 waste material Substances 0.000 description 7
- 238000003756 stirring Methods 0.000 description 5
- 230000001681 protective effect Effects 0.000 description 4
- 239000011358 absorbing material Substances 0.000 description 3
- 230000007797 corrosion Effects 0.000 description 3
- 238000005260 corrosion Methods 0.000 description 3
- 230000008569 process Effects 0.000 description 3
- 229920003002 synthetic resin Polymers 0.000 description 3
- 239000000057 synthetic resin Substances 0.000 description 3
- 229910052902 vermiculite Inorganic materials 0.000 description 3
- 239000010455 vermiculite Substances 0.000 description 3
- 235000019354 vermiculite Nutrition 0.000 description 3
- XEEYBQQBJWHFJM-UHFFFAOYSA-N Iron Chemical compound [Fe] XEEYBQQBJWHFJM-UHFFFAOYSA-N 0.000 description 2
- 230000015572 biosynthetic process Effects 0.000 description 2
- 238000009826 distribution Methods 0.000 description 2
- 230000000694 effects Effects 0.000 description 2
- 238000011049 filling Methods 0.000 description 2
- 239000003973 paint Substances 0.000 description 2
- 230000009467 reduction Effects 0.000 description 2
- KXGFMDJXCMQABM-UHFFFAOYSA-N 2-methoxy-6-methylphenol Chemical class [CH]OC1=CC=CC([CH])=C1O KXGFMDJXCMQABM-UHFFFAOYSA-N 0.000 description 1
- ZCYVEMRRCGMTRW-UHFFFAOYSA-N 7553-56-2 Chemical compound [I] ZCYVEMRRCGMTRW-UHFFFAOYSA-N 0.000 description 1
- 239000004793 Polystyrene Substances 0.000 description 1
- 239000011398 Portland cement Substances 0.000 description 1
- 239000004809 Teflon Substances 0.000 description 1
- 229920006362 Teflon® Polymers 0.000 description 1
- 239000007864 aqueous solution Substances 0.000 description 1
- 239000007900 aqueous suspension Substances 0.000 description 1
- 229910052788 barium Inorganic materials 0.000 description 1
- DSAJWYNOEDNPEQ-UHFFFAOYSA-N barium atom Chemical compound [Ba] DSAJWYNOEDNPEQ-UHFFFAOYSA-N 0.000 description 1
- 230000008901 benefit Effects 0.000 description 1
- 238000005422 blasting Methods 0.000 description 1
- XFWJKVMFIVXPKK-UHFFFAOYSA-N calcium;oxido(oxo)alumane Chemical compound [Ca+2].[O-][Al]=O.[O-][Al]=O XFWJKVMFIVXPKK-UHFFFAOYSA-N 0.000 description 1
- 230000008859 change Effects 0.000 description 1
- 239000003085 diluting agent Substances 0.000 description 1
- 230000008030 elimination Effects 0.000 description 1
- 238000003379 elimination reaction Methods 0.000 description 1
- 231100001261 hazardous Toxicity 0.000 description 1
- 239000004021 humic acid Substances 0.000 description 1
- 238000005470 impregnation Methods 0.000 description 1
- 239000011630 iodine Substances 0.000 description 1
- 229910052740 iodine Inorganic materials 0.000 description 1
- 229910052742 iron Inorganic materials 0.000 description 1
- UQSXHKLRYXJYBZ-UHFFFAOYSA-N iron oxide Inorganic materials [Fe]=O UQSXHKLRYXJYBZ-UHFFFAOYSA-N 0.000 description 1
- 235000013980 iron oxide Nutrition 0.000 description 1
- VBMVTYDPPZVILR-UHFFFAOYSA-N iron(2+);oxygen(2-) Chemical class [O-2].[Fe+2] VBMVTYDPPZVILR-UHFFFAOYSA-N 0.000 description 1
- 238000002386 leaching Methods 0.000 description 1
- 238000004519 manufacturing process Methods 0.000 description 1
- 238000002156 mixing Methods 0.000 description 1
- 239000002245 particle Substances 0.000 description 1
- 230000000737 periodic effect Effects 0.000 description 1
- 239000004033 plastic Substances 0.000 description 1
- -1 poly tetrafluoroethylene Polymers 0.000 description 1
- 229920002223 polystyrene Polymers 0.000 description 1
- 229920001343 polytetrafluoroethylene Polymers 0.000 description 1
- 239000004810 polytetrafluoroethylene Substances 0.000 description 1
- 229940058401 polytetrafluoroethylene Drugs 0.000 description 1
- 239000006100 radiation absorber Substances 0.000 description 1
- 239000002901 radioactive waste Substances 0.000 description 1
- 238000009877 rendering Methods 0.000 description 1
- 238000002791 soaking Methods 0.000 description 1
- 238000003860 storage Methods 0.000 description 1
- 239000000126 substance Substances 0.000 description 1
- 238000005406 washing Methods 0.000 description 1
- XLYOFNOQVPJJNP-UHFFFAOYSA-N water Substances O XLYOFNOQVPJJNP-UHFFFAOYSA-N 0.000 description 1
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
- G21F9/28—Treating solids
- G21F9/34—Disposal of solid waste
-
- C—CHEMISTRY; METALLURGY
- C04—CEMENTS; CONCRETE; ARTIFICIAL STONE; CERAMICS; REFRACTORIES
- C04B—LIME, MAGNESIA; SLAG; CEMENTS; COMPOSITIONS THEREOF, e.g. MORTARS, CONCRETE OR LIKE BUILDING MATERIALS; ARTIFICIAL STONE; CERAMICS; REFRACTORIES; TREATMENT OF NATURAL STONE
- C04B40/00—Processes, in general, for influencing or modifying the properties of mortars, concrete or artificial stone compositions, e.g. their setting or hardening ability
- C04B40/0028—Aspects relating to the mixing step of the mortar preparation
-
- 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
- G21F9/04—Treating liquids
- G21F9/06—Processing
- G21F9/12—Processing by absorption; by adsorption; by ion-exchange
-
- 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
- G21F9/04—Treating liquids
- G21F9/06—Processing
- G21F9/16—Processing by fixation in stable solid media
- G21F9/162—Processing by fixation in stable solid media in an inorganic matrix, e.g. clays, zeolites
- G21F9/165—Cement or cement-like matrix
-
- G—PHYSICS
- G21—NUCLEAR PHYSICS; NUCLEAR ENGINEERING
- G21G—CONVERSION OF CHEMICAL ELEMENTS; RADIOACTIVE SOURCES
- G21G4/00—Radioactive sources
- G21G4/04—Radioactive sources other than neutron sources
-
- C—CHEMISTRY; METALLURGY
- C04—CEMENTS; CONCRETE; ARTIFICIAL STONE; CERAMICS; REFRACTORIES
- C04B—LIME, MAGNESIA; SLAG; CEMENTS; COMPOSITIONS THEREOF, e.g. MORTARS, CONCRETE OR LIKE BUILDING MATERIALS; ARTIFICIAL STONE; CERAMICS; REFRACTORIES; TREATMENT OF NATURAL STONE
- C04B2111/00—Mortars, concrete or artificial stone or mixtures to prepare them, characterised by specific function, property or use
- C04B2111/00474—Uses not provided for elsewhere in C04B2111/00
- C04B2111/00862—Uses not provided for elsewhere in C04B2111/00 for nuclear applications, e.g. ray-absorbing concrete
Landscapes
- Engineering & Computer Science (AREA)
- Chemical & Material Sciences (AREA)
- Physics & Mathematics (AREA)
- General Engineering & Computer Science (AREA)
- High Energy & Nuclear Physics (AREA)
- Ceramic Engineering (AREA)
- General Chemical & Material Sciences (AREA)
- Environmental & Geological Engineering (AREA)
- Chemical Kinetics & Catalysis (AREA)
- Materials Engineering (AREA)
- Structural Engineering (AREA)
- Organic Chemistry (AREA)
- Inorganic Chemistry (AREA)
- Processing Of Solid Wastes (AREA)
- Solid-Sorbent Or Filter-Aiding Compositions (AREA)
- Detergent Compositions (AREA)
- Curing Cements, Concrete, And Artificial Stone (AREA)
Description
DEUTSCHESGERMAN
Die Erfindung stellt eine Abänderung des den Gegenstand der Patentanmeldung A30536VIIIc/21g bildenden Verfahrens zum Unschädlichmachen radioaktiver Flüssigkeit durch Aufsaugenlassen derselben in einem schüttfähigen Aufnahmematerial dar. Wesentlich für das Verfahren der vorgenannten Anmeldung ist, daß gemäß der dortigen Erfindung das schüttfähige Aufnahmematerial zur Erzielung eines reibungslosen, schnellen und gleichmäßigen Aufsaugens, welches ohne Heranziehung mechanischer Hilfsmittel und ohne Rühren weitgehend automatisch verlaufen soll, das strahlenabsorbierende Schweremineral in Gestalt eines im wesentlichen isodispersen Korngemisches enthält. Durch die Verwendung des strahlenabsorbierenden Bestandteils in dieser Form verläuft, wie in der genannten Patentanmeldung dargelegt wird, das Aufsaugenlassen der strahlenden Flüssigkeit oder das Tränken der losen Schütte des Aufnahmematerials mit dieser Flüssigkeit in der gewünschten Weise ohne Bildung von Hohlräumen und ohne die Notwendigkeit des Rührens oder sonstiger mechanischer Nachhilfen.The invention represents a modification of the subject matter of patent application A30536VIIIc / 21g forming process for rendering radioactive liquid harmless by allowing it to be soaked up in a pourable recording material. Essential for the process of the aforementioned application is that according to the invention there, the pourable recording material to achieve a smooth, fast and even suction, which without the use of mechanical Aids and should run largely automatically without stirring, the radiation-absorbing heavy mineral contains in the form of an essentially isodisperse grain mixture. Using the radiation-absorbing component runs in this form, as set out in the patent application mentioned absorbing the radiant liquid or soaking the loose chunks of the Absorbing material with this liquid in the desired manner without the formation of cavities and without the need for stirring or other mechanical aids.
Gemäß der vorliegenden weiteren Erfindung wird diese Eigenschaft der in isodisperser Kornverteilung verwendeten strahlenabsorbierenden Stoffe (also z. B. entsprechend gekörnter Eisenoxyde, Bleierze, hauptsächlich aber von Schwerspat), gleichfalls zum Erzielen eines schnellen Aufsauge- und Tränkungsvorganges ausgenutzt, wobei das genannte isodisperse Korngemisch, welches im Rahmen der vorgenannten Patentanmeldung, zusammen mit losen, hochsaugfähigen Stoffen wie Vermikulit oder Sägemehl, verwendet wurde, nunmehr aber in Gemeinschaft mit einem erhärtenden Bindemittel verwendet wird.According to the present further invention, this property becomes that of isodisperse particle size distribution radiation-absorbing substances used (i.e. e.g. appropriately granulated iron oxides, lead ores, mainly but from heavy spar), also to achieve a quick absorption and impregnation process exploited, said isodisperse grain mixture, which in the context of the aforementioned Patent application, used together with loose, highly absorbent materials such as vermiculite or sawdust but is now used in conjunction with a hardening binder.
Das mit der zu beseitigenden strahlenden Flüssigkeit getränkte Aufnahmematerial wird auf diese Weise verfestigt, und die so entstandenen Blöcke bieten beim Einlagern zum Zwecke des Abstrahlens eine größere Sicherheit gegen unerwünschte Isotopenverluste durch Auswaschen, Absickern u. dgl., als wenn das Aufnahmematerial nur in loser Form zusammen mit der aufgesaugten strahlenden Flüssigkeit in entsprechenden Behältern aufbewahrt würde. Dadurch wird auch das (gegenüber dem Versenken im Meer bedeutend bequemere) Vergraben oder Versenken in der Erde (»Atomfriedhof«) erst gefahrlos ermöglicht und erleichtert.The recording material soaked with the radiant liquid to be removed is applied to this Wise solidified, and the resulting blocks offer when storing for the purpose of blasting greater security against unwanted isotope losses through washing out, seepage, etc., than if the recording material is only in loose form together with the absorbed radiant liquid would be kept in appropriate containers. This also (compared to sinking in Burying or sinking in the earth (»atomic cemetery«) is only safe to do with the sea enables and facilitates.
Eine solche Atommüllbeseitigung kann in der Weise durchgeführt werden, daß zusammen mit dem das Tränken und Aufsaugenlassen erleichternden isodispersen Korngemisch des eigentlichen Strahlenschutzmaterials ein hydraulisches Bindemittel wie Portlandzement, Tonerdezement oder Sorelzement verwendet wird, dessen Gehalt so bemessen ist, daßSuch nuclear waste disposal can be carried out in such a way that together with the das The isodisperse grain mixture of the actual radiation protection material makes it easier to soak and soak it up a hydraulic binder such as portland cement, high alumina cement or sorel cement is used, the content of which is such that
Verfahren zum Beseitigen
radioaktiver FlüssigkeitProcedure for elimination
radioactive liquid
Zusatz zur Zusatzpatentanmeldung A 30536 VIIIc /21g
(Auslegesdirift 1 078 248)Addition to additional patent application A 30536 VIIIc / 21g
(Laying out guide 1 078 248)
Anmelder:Applicant:
Rudolf Alberti,
St. Andreasberg (Harz), Wäschegrund 463Rudolf Alberti,
St. Andreasberg (Harz), laundry ground 463
Rudolf Alberti, St. Andreasberg (Harz),
ist als Erfinder genannt wordenRudolf Alberti, St. Andreasberg (Harz),
has been named as the inventor
die mit der zu beseitigenden wäßrigen, strahlenden Flüssigkeit getränkte lose Schütte des Aufnahmematerials nach einigem Stehenlassen von selbst erhärtet. the loose chute of the recording material soaked with the aqueous, radiant liquid to be removed hardens by itself after standing for a while.
Gemäß einer anderen Ausführungsform kann die Eigenschaft des isodispersen Schweremineral-Korngemisches, insbesondere des Schwerspats, die unschädlich zu machende Flüssigkeit ohne Rühren usw. beim einfachen Einlaufenlassen reibungslos aufzunehmen, auch in der Weise ausgenutzt werden, daß das isodisperse Korngemisch, vorzugsweise Schwerspat, zunächst allein zum Aufsaugen der zu beseitigenden strahlenden Flüssigkeit benutzt und nach dem Trocknen dann durch Zugabe eines Bindemittels, z. B. eines Gießharzes, zum Erhärten gebracht wird. Auf diese Weise lassen sich z. B. Spritzer im »heißen« Laboratorium schnell durch Aufschütten des saugfähigen Korngemisches aufnehmen. Das getränkte Aufnahmematerial wird dann in einem geeigneten Abstellgefäß zunächst getrocknet und dann durch einfaches Übergießen (Einlaufenlassen ohne Rühren) mit einem zunächst flüssigen oder gelösten, dann aber erhärtenden Bindemittel verfestigt. Als Bindemittel kann z. B. ein in geeigneter gießfähiger Form verwendetes Gießharz des Handels dienen, wie das unter dem warenzeichenrechtlich geschützten Namen »Palatal« bekannte Kunstharz auf Polystyrolgrundlage. Auch ein mit organischen Verdünnungsmitteln gießbar gehaltenes modifiziertes Phenolharz, wie es unter dem Warenzeichen »Asplit« im Handel ist, eignet sich (neben unzähligen weiteren Kunstharzen) als Bindemittel für die genannten Zwecke.According to another embodiment, the property of the isodisperse heavy mineral grain mixture, especially the barite, the liquid to be rendered harmless without stirring, etc. simple running-in can also be used in such a way that the isodisperse Mixture of grains, preferably barite, initially solely for vacuuming up those to be removed used radiant liquid and then after drying by adding a binder, e.g. B. one Cast resin, is brought to harden. In this way, z. B. Splashes in the "hot" laboratory absorb quickly by pouring up the absorbent grain mixture. The soaked recording material is then first dried in a suitable storage container and then simply poured over (Let it run in without stirring) with an initially liquid or dissolved, but then hardening Binder solidifies. As a binder, for. B. a casting resin used in a suitable castable form for trade, as is known under the trademarked name »Palatal« Polystyrene-based synthetic resin. Also one that is kept pourable with organic diluents Modified phenolic resin, as it is commercially available under the trademark »Asplit«, is suitable (in addition to countless other synthetic resins) as binders for the purposes mentioned.
An sich ist es bekannt, Atommüll, der in wäßriger Lösung oder Suspension vorliegt, mit Zement ab-It is known per se to remove nuclear waste in an aqueous solution or suspension with cement.
009 529/227009 529/227
binden zu lassen und die so entstandenen Blöcke dann unter' geeigneten Schutzmaßnahmen abzutransportieren und gegebenenfalls ins Meer zu versenken. Die erhebliche Abstrahlung, die aus diesen Zementblöcken austritt, macht das Umgehen mit diesen aber sehr umständlich, da umfangreiche Schutzmaßnahmen gegen die gefährliche austretende Strahlung getroffen werden müssen. Dadurch, daß aber nun innerhalb solcher z. B. hydraulisch abgebundenen Atommüllblöcke wesentliche Mengen hochstrahlenabsorbierender Bestandteile, wie z. B. Schwerspat, miteingebunden sind, wird bereits ein beträchtlicher Teil der Abstrahlung unschädlich gemacht, so daß also die zusätzlich anzuwendenden Schutzmaßnahmen für die Erzielung einer gegebenen gleichen Strahlungsverminderung entsprechend eingeschränkt werden können, wie es in der deutschen Patentanmeldung A 25773 VIIIc/21g, der Hauptpatentanmeldung für die eingangs erwähnte Zusatzpatentanmeldung A 30536 VIIIc/21g, im einzelnen dargelegt ist. Dadurch, daß nun weiter dieser die Abstrahlung herabsetzende Gehalt der verfestigten Blöcke in Form eines isodispersen Korngemisches gemäß der genannten Zusatzpatentanmeldung A 30536 VIIIc/21g verwendet wird, entfallen nun auch die weiteren Schwierigkeiten, die bei der bisher gebräuchlichen Anfertigung der mit Zement verfestigten Atommüllblöcke verbunden waren, nämlich die Notwendigkeit des Rührens oder sonstiger Nachhilfen für die gleichmäßige Vermischung des Bindemittels mit der strahlenden Flüssigkeit. Das isodisperse Korngemisch ermöglicht das Aufsaugenlassen der strahlenden Flüssigkeit ohne jede äußere Nachhilfe in kürzester Zeit und ohne die Bildung von Hohlräumen und schlecht benetzten Teilen der Aufnahmeschütte.to let bind and then to transport the resulting blocks under 'suitable protective measures and if necessary to sink into the sea. The significant radiation emanating from these cement blocks escapes, but makes dealing with them very cumbersome, as extensive protective measures against the dangerous emitted radiation must be met. By the fact that but now within such z. B. hydraulically bound nuclear waste blocks substantial amounts of highly radiation-absorbing components, such as B. barite, are involved, a considerable part of the radiation is already harmless made, so that the additional protective measures to be applied to achieve a given the same radiation reduction can be restricted accordingly, as in the German patent application A 25773 VIIIc / 21g, the main patent application for the aforementioned Additional patent application A 30536 VIIIc / 21g, in detail is set out. As a result of the fact that this radiation-reducing content of the solidified Blocks in the form of an isodisperse grain mixture according to the additional patent application A 30536 mentioned VIIIc / 21g is used, the other difficulties that have been encountered with the previously used Manufacture of cement-solidified nuclear waste blocks were connected, namely the need of stirring or other aids for the even mixing of the binder with the radiant liquid. The isodisperse mixture of grains enables the radiating liquid to be absorbed without any outside tutoring in the shortest possible time and without the formation of cavities and bad wetted parts of the receiving chute.
Der auch schon in der genannten früheren Patentanmeldung als besonders wohlfeiles Aufnahmematerial empfohlene gekörnte Schwerspat hat anderen strahlenabsorbierenden Materialien von hohem spezifischem Gewicht gegenüber noch den weiteren Vorteil, daß infolge der hohen Ordnungszahl (56) des Bariums im Periodischen System der Elemente weiche, also langwellige Strahlen, wie sie z. B. von aktivem Jod ausgesandt werden, besonders gut absorbiert werden.The one already mentioned in the earlier patent application mentioned as particularly inexpensive recording material Recommended granular barite has other radiation-absorbing materials of high specificity Weight compared to the further advantage that due to the high atomic number (56) of the barium in the Periodic system of the elements soft, i.e. long-wave rays, such as those found in e.g. B. sent out by active iodine are particularly well absorbed.
Das geschilderte Verfahren zum Beseitigen radioaktiver Flüssigkeiten kann z. B. durchgeführt werden mit Hilfe eines verzinkten Eisenrohres von 1 mm Wandstärke, 1 m Höhe und 15 cm lichter Weite. Eine solche Trommel, wie sie in bedeutenden Isotopenlaboratorien zum Beseitigen strahlender Abfälle gebräuchlich ist, wird mit dem schüttfähigen Aufnahmematerial beschickt, bestehend aus 36 kg einer im wesentlichen isodispersen Schwerspatkörnung einer Korngröße zwischen 1,5 und 2,8 mm, vermischt mit 6,2 kg Tonerdezement. Die so mit saugfähigem Material gefüllte Röhre kann 3 bis 5 1 strahlenden Wassers aufnehmen, wobei zum Abbinden an sich 3 1 genügen. Nach mehrtägigem Stehen ist der Röhreninhalt dann abgebunden.The described method for the disposal of radioactive liquids can, for. B. be carried out with the help of a galvanized iron pipe with a wall thickness of 1 mm, a height of 1 m and a clearance of 15 cm. One such a drum, as used in major isotope laboratories for the removal of radioactive waste is, is charged with the pourable receiving material, consisting of 36 kg of a substantially isodisperse heavy spar grains with a grain size between 1.5 and 2.8 mm, mixed with 6.2 kg of calcium aluminate cement. The tube filled with absorbent material can hold 3 to 5 liters of radiating water record, with 3 1 being sufficient for setting. After standing for several days, the tube is empty then tied.
Die in dieser Weise mit dem Atommüll gefüllte Trommel kann abtransportiert und beispielsweise in der Erde vergraben oder versenkt werden. Um auch für längere Zeit Sicherung gegen Auslaugen und gegen korrodierende Angriffe des Trommelmantels zu bieten, kann dieser innen mit einem korrosionsfesten Anstrich oder einer Auskleidung versehen werden, z. B. aus dem oben bereits erwähnten Gießharz »Asplit« oder dem korrosionsfesten Kunststoff »Teflon« (eingetragenes Warenzeichen), einem Poly tetrafluorethylen. Ebenso kann die Trommel einen korrosionsfesten Außenanstrich aus Kunstharz erhalten, der sie gegen den Einfluß von Atmosphärilien, Alkalien, Humussäuren u. dgl. schützt. Dadurch, daß außerdem der Inhalt der Trommel nicht nur wie bisher aus losem, mit der strahlenden Flüssigkeit getränktem Aufnahmematerial besteht, sondern durch die Anwesenheit des hydraulischen Bindemittels verfestigt ist, wird offensichtlich auch für den Fall einer Beschädigung der Hülle oder eines Undichtwerdens die Gefahr von Verlusten und Ausspülungen des gefährlichen strahlenden Materials wesentlich herabgesetzt. The drum filled with the nuclear waste in this way can be transported away and, for example, in buried or sunk in the earth. In order to protect against leaching and for a longer period of time To protect the drum shell from corrosive attacks, it can be coated inside with a corrosion-resistant Paint or a lining are provided, e.g. B. from the casting resin already mentioned above »Asplit« or the corrosion-resistant plastic »Teflon« (registered trademark), a poly tetrafluoroethylene. The drum can also be given a corrosion-resistant synthetic resin paint on the outside, which protects them against the influence of atmospheres, alkalis, humic acids and the like. As a result of that In addition, the contents of the drum not only consist of loose items soaked in the radiant liquid, as was previously the case Absorbing material consists, but solidified by the presence of the hydraulic binder is also evident in the event of damage to the envelope or leakage the risk of loss and washout of the hazardous radiating material is significantly reduced.
Gegenüber der früher gebräuchlichen Methode, derartige Trommeln nur mit losem, schüttfähigem Aufsaugmaterial, wie z. B. Vermikulit, zu füllen und die zu beseitigende Flüssigkeit von dieser Füllung aufsaugen zu lassen, wird durch den jetzt angewandten Gehalt des Aufnahmematerials an isodispers verteilter Schwerspatkörnung die Abstrahlung aus der gefüllten Trommel so herabgesetzt, daß der für den Transport dieser Trommeln gebräuchliche Schutzmantel aus Barytbeton für eine gegebene Strahlungsminderung an der Außenfläche schwächer gehalten werden kann, so daß also die Wirtschaftlichkeit dieser Isotopenmüllbeseitigung wesentlich erhöht wird. Rechnung und Versuche haben ergeben, daß man bei gleicher Außenabmessung der Barytbetonhülle und bei gleichem Strahlungswert an deren Oberfläche den Aufnahmeraum für aktive Flüssigkeit, also den Innenraum der Trommel, um 40% steigern kann gegenüber dem bisherigen Verfahren mit reiner Vermikulitfüllung der Innentrommel. Und zwar wird dieses für die Wirtschaftlichkeit der Atommüllbeseitigung wichtige Ergebnis erzielt, ohne daß durch den strahlenabsorbierenden Gehalt des Aufnahmematerials das schnelle und ohne Rühren oder sonstige Hilfsmittel vor sich gehende Aufsaugen der strahlenden Flüssigkeit im Trommelinhalt behindert wird (Wirkung der isodispersen Kornverteilung des Strahlenschutzmaterials) und ohne daß die Gefahr besteht, daß bei einem späteren Undichtwerden der Aufnahmetrommel der gefährliche Inhalt austreten könnte oder ausgewaschen werden könnte (Wirkung der gleichzeitig verwendeten erhärtenden Bindemittel).Compared to the previously common method, such drums only with loose, pourable absorbent material, such as B. vermiculite to fill and soak up the liquid to be removed from this filling isodisperse because of the isodisperse content of the recording material that is now used Heavy spar grains reduce the radiation from the filled drum so that the for the Transport of these drums customary protective jacket made of barite concrete kept weaker on the outer surface for a given reduction in radiation can be, so that the economic efficiency of this isotope waste disposal is significantly increased will. Calculations and tests have shown that with the same external dimensions of the barite concrete shell and with the same radiation value on their surface the space for active liquid, i.e. the interior of the drum, can be increased by 40% compared to the previous method with pure vermiculite filling of the inner drum. And indeed will achieved this result, which is important for the economy of nuclear waste disposal, without being through the radiation-absorbing content of the recording material quickly and without stirring or other Aids in progress absorption of the radiating liquid in the drum contents is hindered (Effect of the isodisperse grain distribution of the radiation protection material) and without the risk of that in the event of a later leak in the receiving drum, the dangerous content could escape or could be washed out (effect of the hardening binders used at the same time).
Je nach den Bedingungen des Einzelfalles und den gewünschten Saugeigenschaften des Aufnahmematerials kann die Korngröße des isodispersen Strahlenabsorptionsmittels, insbesondere des Schwerspats, in den in der früheren Patentanmeldung genannten Grenzen von etwa 0,3 bis 3,5 mm gewählt werden.Depending on the conditions of the individual case and the desired suction properties of the recording material can change the grain size of the isodisperse radiation absorber, in particular the heavy spar, in the in the earlier patent application mentioned limits of about 0.3 to 3.5 mm can be selected.
Claims (3)
Priority Applications (15)
| Application Number | Priority Date | Filing Date | Title |
|---|---|---|---|
| NL235423D NL235423A (en) | 1959-01-19 | ||
| DEA25773A DE1053686B (en) | 1956-10-01 | 1956-10-01 | Process and device for rendering radioactive isotope waste harmless |
| GB30393/57A GB871336A (en) | 1959-01-19 | 1957-09-27 | Improved method of handling radioactive material |
| US687316A US2961399A (en) | 1959-01-19 | 1957-09-30 | Method for neutralizing obnoxious radiation |
| DEA30536A DE1078248B (en) | 1958-10-15 | 1958-10-15 | Procedure for rendering radioactive liquid harmless |
| DEA31154A DE1082993B (en) | 1959-01-19 | 1959-01-19 | Procedure for disposal of radioactive liquid |
| FR1214570D FR1214570A (en) | 1959-01-19 | 1959-01-23 | Method and device for rendering radioactive isotope waste non-harmful |
| DEA32425A DE1109279B (en) | 1959-01-19 | 1959-07-08 | Process for solidifying liquid nuclear waste |
| GB1774/60A GB929863A (en) | 1959-01-19 | 1960-01-18 | Improvements in and relating to the disposal of radioactive waste |
| DEA34361A DE1166392B (en) | 1959-01-19 | 1960-04-02 | Process and device for the disposal of aqueous nuclear waste |
| DEA35632A DE1127508B (en) | 1959-01-19 | 1960-09-22 | Process and device for solidifying aqueous nuclear waste |
| DEA36998A DE1199414B (en) | 1959-01-19 | 1961-03-18 | Process for solidifying aqueous atomic waste |
| GB11579/61A GB938211A (en) | 1959-01-19 | 1961-03-29 | Improvements in methods of solidifying watery atomic waste |
| FR857294A FR1285130A (en) | 1959-01-19 | 1961-03-30 | Method and device for the removal or solidification of aqueous atomic waste |
| NL263076A NL263076A (en) | 1959-01-19 | 1961-03-30 |
Applications Claiming Priority (4)
| Application Number | Priority Date | Filing Date | Title |
|---|---|---|---|
| DEA31154A DE1082993B (en) | 1959-01-19 | 1959-01-19 | Procedure for disposal of radioactive liquid |
| DEA32425A DE1109279B (en) | 1959-01-19 | 1959-07-08 | Process for solidifying liquid nuclear waste |
| DEA34361A DE1166392B (en) | 1959-01-19 | 1960-04-02 | Process and device for the disposal of aqueous nuclear waste |
| DEA35632A DE1127508B (en) | 1959-01-19 | 1960-09-22 | Process and device for solidifying aqueous nuclear waste |
Publications (1)
| Publication Number | Publication Date |
|---|---|
| DE1082993B true DE1082993B (en) | 1960-06-09 |
Family
ID=27436530
Family Applications (4)
| Application Number | Title | Priority Date | Filing Date |
|---|---|---|---|
| DEA31154A Pending DE1082993B (en) | 1956-10-01 | 1959-01-19 | Procedure for disposal of radioactive liquid |
| DEA32425A Pending DE1109279B (en) | 1956-10-01 | 1959-07-08 | Process for solidifying liquid nuclear waste |
| DEA34361A Pending DE1166392B (en) | 1956-10-01 | 1960-04-02 | Process and device for the disposal of aqueous nuclear waste |
| DEA35632A Pending DE1127508B (en) | 1956-10-01 | 1960-09-22 | Process and device for solidifying aqueous nuclear waste |
Family Applications After (3)
| Application Number | Title | Priority Date | Filing Date |
|---|---|---|---|
| DEA32425A Pending DE1109279B (en) | 1956-10-01 | 1959-07-08 | Process for solidifying liquid nuclear waste |
| DEA34361A Pending DE1166392B (en) | 1956-10-01 | 1960-04-02 | Process and device for the disposal of aqueous nuclear waste |
| DEA35632A Pending DE1127508B (en) | 1956-10-01 | 1960-09-22 | Process and device for solidifying aqueous nuclear waste |
Country Status (5)
| Country | Link |
|---|---|
| US (1) | US2961399A (en) |
| DE (4) | DE1082993B (en) |
| FR (1) | FR1214570A (en) |
| GB (3) | GB871336A (en) |
| NL (2) | NL263076A (en) |
Cited By (4)
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| DE1166946B (en) * | 1961-01-10 | 1964-04-02 | Gustav Boecker | Process and device for transferring radioactive waste into a form suitable for storage and further use |
| FR2317739A1 (en) * | 1975-07-11 | 1977-02-04 | Kernforschungsanlage Juelich | PROCESS FOR SOLIDIFYING RESIDUES, SUCH AS AQUEOUS SOLUTIONS CONTAINING RADIOACTIVE OR TOXIC SUBSTANCES |
| FR2424611A1 (en) * | 1978-04-29 | 1979-11-23 | Kernforschungsz Karlsruhe | PROCESS FOR THE SOLIDIFICATION FOR THE END STORAGE, FAVORABLE TO THE ENVIRONMENT, OF AQUEOUS RADIO-ACTIVE LIQUID WASTE OF MEDIUM (MAW) AND LOW (LAW) ACTIVITY CATEGORIES, AND OF LIQUIDS CONTAINING TRITIUM COMPOUNDS |
| US4594186A (en) * | 1982-04-26 | 1986-06-10 | Kernforschungszentrum Karlsruhe Gmbh | Method for improving the radionuclide retention properties of solidified radioactive wastes |
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| NL271326A (en) * | 1958-12-31 | |||
| DE1199414B (en) | 1959-01-19 | 1965-08-26 | Rudolf Alberti | Process for solidifying aqueous atomic waste |
| NL235423A (en) | 1959-01-19 | |||
| US3116131A (en) * | 1960-08-01 | 1963-12-31 | Victor Comptometer Corp | Method and materials for disposing of radioactive waste |
| US3006777A (en) * | 1960-08-22 | 1961-10-31 | American Nuclear Shield Corp | Building materials |
| US3213031A (en) * | 1961-08-28 | 1965-10-19 | Pullman Inc | Method of sealing refractory vessel containing radioactive wastes |
| US3303140A (en) * | 1961-12-05 | 1967-02-07 | Pullman Inc | Radioactive materials of low surface area |
| NL292712A (en) * | 1962-05-14 | |||
| US3330088A (en) * | 1964-12-23 | 1967-07-11 | Jr John V Dunlea | Method of bulk rubbish disposal |
| GB1054740A (en) * | 1964-12-29 | |||
| FR1438454A (en) * | 1965-03-30 | 1966-05-13 | Commissariat Energie Atomique | Improvements to processes for injecting radioactive waste into the soil |
| US3272756A (en) * | 1965-08-31 | 1966-09-13 | John D Kaser | Radioactive waste disposal using colemanite |
| US3992216A (en) * | 1974-07-24 | 1976-11-16 | Kirschner Leon I | Lightweight aggregate for concrete and method for making same |
| US4188232A (en) * | 1974-09-16 | 1980-02-12 | Hall William C | Mini-aggregate iron ore in cement matrix |
| USD244393S (en) | 1975-01-06 | 1977-05-17 | Medi-Ray, Inc. | Waste container for radioactive material |
| US3988258A (en) | 1975-01-17 | 1976-10-26 | United Nuclear Industries, Inc. | Radwaste disposal by incorporation in matrix |
| US3983050A (en) * | 1975-02-07 | 1976-09-28 | The United States Of America As Represented By The United States Energy Research And Development Administration | Method for storage of solid waste |
| DE2515795A1 (en) * | 1975-04-11 | 1976-10-14 | Licentia Gmbh | METHOD FOR TREATMENT OF RADIOACTIVE CONCENTRATES |
| US4054320A (en) * | 1976-08-24 | 1977-10-18 | United States Steel Corporation | Method for the removal of radioactive waste during in-situ leaching of uranium |
| DE2819085C3 (en) * | 1978-04-29 | 1981-04-23 | Kernforschungszentrum Karlsruhe Gmbh, 7500 Karlsruhe | Process for the environmentally friendly solidification of highly and moderately radioactive and / or actinide-containing aqueous waste concentrates or of fine-grain solid waste suspended in water in a manner that is ready for final disposal |
| US4113504A (en) * | 1977-10-03 | 1978-09-12 | Stauffer Chemical Company | Disposal of heavy metal containing sludge wastes |
| US4174293A (en) * | 1977-10-12 | 1979-11-13 | The United States Of America As Represented By The United States Department Of Energy | Process for disposal of aqueous solutions containing radioactive isotopes |
| DE2748098A1 (en) * | 1977-10-27 | 1979-05-10 | Kernforschungsz Karlsruhe | PROCESS FOR IMPROVING THE LEAKAGE RESISTANCE OF BITUMEN FASTENING PRODUCTS |
| GB2048555A (en) * | 1979-05-02 | 1980-12-10 | British Nuclear Fuels Ltd | Plutonium waste fixation |
| DE3047697A1 (en) * | 1980-12-18 | 1982-07-15 | Deutsche Gesellschaft für Wiederaufarbeitung von Kernbrennstoffen mbH, 3000 Hannover | "DEVICE FOR RECEIVING AND TRANSPORTING RADIOACTIVE LIQUIDS" |
| DE3048001A1 (en) * | 1980-12-19 | 1982-07-01 | Kernforschungszentrum Karlsruhe Gmbh, 7500 Karlsruhe | METHOD FOR THE PRODUCTION OF REAL-END BEARING TIRES, RADIOACTIVE MATERIALS WITH WASTE FASTENING PRODUCTS WITH INCREASED RADIATION RESISTANCE OR. REDUCED RADIOLYSE GAS FORMATION FROM THE CATEGORY OF RADIOACTIVE WASTE SHAPED BODIES STRENGTHENED WITH HYDRAULICALLY SETTING, HARDENING, INORGANIC MATERIALS |
| JPS5962343A (en) * | 1982-10-01 | 1984-04-09 | Hitachi Ltd | Inorganic adsorbent and its manufacturing method and its usage method |
| US4591455A (en) * | 1982-11-24 | 1986-05-27 | Pedro B. Macedo | Purification of contaminated liquid |
| JPS6013172A (en) * | 1983-07-04 | 1985-01-23 | 旭化成株式会社 | Static destruction of concrete and expansion tablet |
| DE3545592C1 (en) * | 1985-12-21 | 1987-06-25 | Nukem Gmbh | Process for conditioning water-soluble special waste |
| FR2607957A1 (en) * | 1986-12-05 | 1988-06-10 | Commissariat Energie Atomique | BLOCK CONTAINING WASTE FOR THEIR STORAGE AND METHOD OF MAKING SUCH A BLOCK |
| US4828761A (en) * | 1988-05-04 | 1989-05-09 | The United States Of America As Represented By The United States Department Of Energy | Process for impregnating a concrete or cement body with a polymeric material |
| DE3842215A1 (en) * | 1988-12-15 | 1990-06-21 | Bayer Ag | METHOD FOR DEPOSITING WASTE |
| US5328028A (en) * | 1989-08-22 | 1994-07-12 | Greif Bors. Corporation | Hazardous waste disposal method and drum assembly |
| GB9319196D0 (en) * | 1993-09-16 | 1993-11-03 | British Nuclear Fuels Plc | Grouting materials and their use |
| GB9511700D0 (en) * | 1995-06-09 | 1995-08-02 | Sandoz Ltd | Improvements in or relating to organic compounds |
| DE19815378A1 (en) * | 1998-04-06 | 1999-10-21 | Herding Gmbh | Porous, dimensionally stable molded body |
| CN103447012B (en) * | 2013-07-23 | 2015-08-12 | 中电信嘉(北京)环保科技有限公司 | For removing filter medium of radioactive radon in drinking water and preparation method thereof |
| CN107459250A (en) * | 2017-09-25 | 2017-12-12 | 常州苏通海平机电科技有限公司 | A kind of preparation method of sewage dehydrating agent |
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| US2682268A (en) * | 1950-08-08 | 1954-06-29 | Abbott Lab | Venoclysis equipment |
| US2616847A (en) * | 1951-04-27 | 1952-11-04 | William S Ginell | Disposal of radioactive cations |
| BE553665A (en) * | 1955-12-23 | |||
| DE1053686B (en) * | 1956-10-01 | 1959-03-26 | Rudolf Alberti | Process and device for rendering radioactive isotope waste harmless |
| FR1213496A (en) | 1958-08-08 | 1960-04-01 | Commissariat Energie Atomique | Water and vapor separator cyclone for boiling water atomic reactor cell |
| DE1078248B (en) * | 1958-10-15 | 1960-03-24 | Rudolf Alberti | Procedure for rendering radioactive liquid harmless |
| NL235423A (en) | 1959-01-19 |
-
0
- NL NL235423D patent/NL235423A/xx unknown
-
1957
- 1957-09-27 GB GB30393/57A patent/GB871336A/en not_active Expired
- 1957-09-30 US US687316A patent/US2961399A/en not_active Expired - Lifetime
-
1959
- 1959-01-19 DE DEA31154A patent/DE1082993B/en active Pending
- 1959-01-23 FR FR1214570D patent/FR1214570A/en not_active Expired
- 1959-07-08 DE DEA32425A patent/DE1109279B/en active Pending
-
1960
- 1960-01-18 GB GB1774/60A patent/GB929863A/en not_active Expired
- 1960-04-02 DE DEA34361A patent/DE1166392B/en active Pending
- 1960-09-22 DE DEA35632A patent/DE1127508B/en active Pending
-
1961
- 1961-03-29 GB GB11579/61A patent/GB938211A/en not_active Expired
- 1961-03-30 NL NL263076A patent/NL263076A/xx unknown
Cited By (4)
| Publication number | Priority date | Publication date | Assignee | Title |
|---|---|---|---|---|
| DE1166946B (en) * | 1961-01-10 | 1964-04-02 | Gustav Boecker | Process and device for transferring radioactive waste into a form suitable for storage and further use |
| FR2317739A1 (en) * | 1975-07-11 | 1977-02-04 | Kernforschungsanlage Juelich | PROCESS FOR SOLIDIFYING RESIDUES, SUCH AS AQUEOUS SOLUTIONS CONTAINING RADIOACTIVE OR TOXIC SUBSTANCES |
| FR2424611A1 (en) * | 1978-04-29 | 1979-11-23 | Kernforschungsz Karlsruhe | PROCESS FOR THE SOLIDIFICATION FOR THE END STORAGE, FAVORABLE TO THE ENVIRONMENT, OF AQUEOUS RADIO-ACTIVE LIQUID WASTE OF MEDIUM (MAW) AND LOW (LAW) ACTIVITY CATEGORIES, AND OF LIQUIDS CONTAINING TRITIUM COMPOUNDS |
| US4594186A (en) * | 1982-04-26 | 1986-06-10 | Kernforschungszentrum Karlsruhe Gmbh | Method for improving the radionuclide retention properties of solidified radioactive wastes |
Also Published As
| Publication number | Publication date |
|---|---|
| DE1109279B (en) | 1961-06-22 |
| FR1214570A (en) | 1960-04-11 |
| DE1127508B (en) | 1962-04-12 |
| US2961399A (en) | 1960-11-22 |
| GB871336A (en) | 1961-06-28 |
| NL235423A (en) | |
| NL263076A (en) | 1964-05-25 |
| DE1166392B (en) | 1964-03-26 |
| GB929863A (en) | 1963-06-26 |
| GB938211A (en) | 1963-10-02 |
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