EP0355514A2 - Process for conditioning radioactive evaporator concentrates form nuclear plants - Google Patents

Process for conditioning radioactive evaporator concentrates form nuclear plants Download PDF

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Publication number
EP0355514A2
EP0355514A2 EP89114316A EP89114316A EP0355514A2 EP 0355514 A2 EP0355514 A2 EP 0355514A2 EP 89114316 A EP89114316 A EP 89114316A EP 89114316 A EP89114316 A EP 89114316A EP 0355514 A2 EP0355514 A2 EP 0355514A2
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Prior art keywords
evaporator
final storage
concentrate
repository
storage container
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EP89114316A
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German (de)
French (fr)
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EP0355514A3 (en
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Dieter Dipl.-Ing. Feyerbacher
Stefan Dipl.-Ing. Rosenberger
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Nukem GmbH
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Nukem GmbH
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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
    • G21F9/04Treating liquids
    • G21F9/06Processing
    • G21F9/08Processing by evaporation; by distillation

Definitions

  • the present invention relates to a method for conditioning radioactive evaporator liquors, optionally together with spherical resins, diatomaceous earth and filter aids from nuclear plants for the purpose of confinement by disposal in a heatable repository package.
  • Radioactive evaporator liquors or mixtures of evaporator liquors with spherical resins, diatomaceous earth and filter aids are usually already used in the nuclear facilities, e.g. in nuclear power plants, concentrated to a dry matter content of approx. 20-25% by weight. They have to be concentrated further by evaporation in order to prepare them for disposal in appropriate containers.
  • DE-PS 32 00 331 describes a process by which evaporator concentrates are dried in a heated repository vessel. Disadvantages of this process, however, are the relatively low evaporation rate and the formation of cavities, some of which are of considerable size, which are also distributed irregularly in the solidified product. This results in poor utilization of the container volume and an unfavorable economy.
  • DE-OS 3544270 describes a drying process in which microwave energy is used for drying, liquids and solutions being sprayed into the container and solidified in one step. This process is very complex and therefore has economic disadvantages.
  • This object is achieved in that the liquor or the mixture is first concentrated to 60 to about 85% by weight dry matter content in an evaporator, then the still flowable concentrate is poured into the heatable final storage container, and finally the concentrate in the final storage container at least the maximum temperature occurring in the repository is heated and the steam produced is suctioned off under reduced pressure until a solid floor body with a smooth surface has formed.
  • the concentrate is preferably heated to the maximum temperature occurring in the repository.
  • radioactive evaporator liquor (11), spherical resins (12) and filter aids (13) from nuclear power plants or other nuclear facilities are conveyed into an evaporator (1) which is operated with a stirrer (9) , a droplet separator (10), a condenser (7) and a distillate collector (8) is provided, from which the distillate can be removed in a controlled manner.
  • the mixture (3) is heated with stirring and concentrated until the concentrate contains 60 to about 85% by weight of dry substance.
  • the residual water still present in the concentrate which is viscous at the evaporator temperature and solid at room temperature, consists essentially of water of crystallization of the salt component.
  • the viscous concentrate is then discharged in portions into a final storage container (2) provided with a heater (4).
  • the first portion (5) is heated by the supply of heat as long and so high that the crystal water content is expelled from the concentrate to such an extent that a solid monolithic soil body with a smooth surface and without powdery components forms in the final storage container (2).
  • This floor must remain firm even at the maximum temperature occurring in the repository, so that the evaporation temperature in the repository package (2) must be at least as high as the maximum temperature to be expected in the repository. Evaporation temperatures of about 70 ° C.
  • a boiling water reactor-simulate mixture of evaporator liquors, ion exchanger spherical resins and filter aids was first concentrated in an evaporator.
  • the resulting concentrate had the composition: Na2SO4 50% by weight Spherical resins 15% by weight Na3PO4 5% by weight Ca3 (PO4) 2 1.5% by weight Fe2O3 1.5% by weight Other 2.0% by weight Residual water 25% by weight
  • This concentrate was drained in portions into a heated repository and solidified at 80 o C at 300 HPa.
  • the end product had a residual water content of about 8% and had a microporous structure without voids and inhomogeneities.
  • the end product surface was smooth, the abrasion and pressure resistance good.
  • the geometric shape did not change during acceleration tests. Heating tests at 70 o C, which correspond to final storage conditions, showed that the solidification product did not change its consistency.

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  • Physics & Mathematics (AREA)
  • Engineering & Computer Science (AREA)
  • General Engineering & Computer Science (AREA)
  • High Energy & Nuclear Physics (AREA)
  • Vaporization, Distillation, Condensation, Sublimation, And Cold Traps (AREA)
  • Fertilizers (AREA)

Abstract

Radioactive evaporator concentrates from nuclear plants are conditioned for ultimate disposal in heatable ultimate storage containers. For this purpose 60 to 85% by weight of dry matter content is firstly concentrated in an evaporator, and then water vapour is extracted in the ultimate storage vessel at a temperature which corresponds at least to the maximum temperature occurring in the ultimate repository until solid bottoms with a smooth surface are produced. <IMAGE>

Description

Gegenstand der vorliegenden Erfindung ist ein Verfahren zum Konditionieren von radioaktiven Verdampferlaugen, gegebenenfalls zusammen mit Kugelharzen, Kieselgur und Filterhilfsmitteln aus kerntechnischen Anlagen zum Zweck der endlagerfähigen Einschließung durch Eindampfen in einem beheizbaren Endlagergebinde.The present invention relates to a method for conditioning radioactive evaporator liquors, optionally together with spherical resins, diatomaceous earth and filter aids from nuclear plants for the purpose of confinement by disposal in a heatable repository package.

Radioaktive Verdampferlaugen bzw. Gemische aus Verdampferlaugen mit Kugelharzen, Kieselgur und Filterhilfsmitteln werden üblicherweise bereits in den kerntechnischen Anlagen, z.B. in Kernkraftwerken, auf einen Trockensubstanzgehalt von ca. 20-25 Gew. % eingeengt. Sie müssen durch Eindampfen weiter konzentriert werden, um sie endlagerfähig in entsprechenden Gebinden aufzubereiten.Radioactive evaporator liquors or mixtures of evaporator liquors with spherical resins, diatomaceous earth and filter aids are usually already used in the nuclear facilities, e.g. in nuclear power plants, concentrated to a dry matter content of approx. 20-25% by weight. They have to be concentrated further by evaporation in order to prepare them for disposal in appropriate containers.

Bis auf 10-40 Gew. % Restwasser eingedampfte Konzentrate weisen bei Raumtemperatur eine monolithische Struktur auf, bei der das Restwasser im wesentlichen als Kristallwasser in der Masse gebunden ist. Bei höheren Temperaturen, z.B. bei einer Endlagertemperatur bis etwa 70o C (Nachbetriebsphase in der Endlagerstätte) werden die festen Salzblöcke jedoch durch das freiwerdende Kristallwasser wieder zähflüssig. Die Endlagerung solcher flüssigwerdenden Salzblöcke ist jedoch nicht zulässig.Concentrates evaporated down to 10-40% by weight of residual water have a monolithic structure at room temperature, in which the residual water is essentially bound as bulk water. At higher temperatures, for example at a repository temperature of up to about 70 o C (post-operation phase in the repository), however, the solid salt blocks become viscous again due to the crystal water released. However, the final storage of such liquid salt blocks is not permitted.

Zur weiteren Einengung von in Kernkraftwerken aus Sumpf-, Wasch-, Deko- und Laborabwässern anfallenden Verdampferkonzentraten sind mehrere einstufige Verfahren bekannt. So gibt es beispielsweise Verfahren, bei denen die Konzentrate in einem geeigneten Verdampfer zur Trockne eingedampft werden. Verwendet werden dazu beispielsweise Rührkesselverdampfer, Sprühtrockner, Walzentrockner und Dünnschichtverdampfer. Das dabei entstehende Produkt mit minimalen Kristallwasserwerten fällt weitgehend pulverförmig an. Das hat zum einen den Nachteil, daß der Umgang mit derartig staubenden Pulvern besondere Schutzmaßnahmen erforderlich machen, um Inkorporationen zu vermeiden; zum anderen folgt aus den niedrigen Schüttdichten von Pulvern, daß das Endlagergebindevolumen nur schlecht ausgenutzt wird. Das Vermischen dieser Pulver mit Zuschlagstoffen (z.B. Bitumen), um sie zu verfestigen, bedeutet ebenso eine schlechte Gebindeausnutzung.Several further single-stage processes are known for further concentration of evaporator concentrates produced in sump, washing, decorative and laboratory wastewater in nuclear power plants. For example, there are processes in which the concentrates are evaporated to dryness in a suitable evaporator. For this purpose, for example, stirred tank evaporators, spray dryers, drum dryers and thin-film evaporators are used. The resulting product with minimal crystal water values is largely powdery. On the one hand, this has the disadvantage that handling such dusty powders necessitates special protective measures in order to avoid incorporations; on the other hand, it follows from the low bulk densities of powders that the volume of the repository is poorly used. Mixing these powders with additives (e.g. bitumen) to solidify them also means poor container utilization.

In der DE-PS 32 00 331 wird ein Verfahren beschrieben, nach dem in einem beheizten Endlagergefäß Verdampferkonzentrate getrocknet werden. Nachteilig bei diesem Verfahren sind jedoch die relativ niedrige Ausdampfleistung sowie die Bildung von Lunkern zum Teil erheblicher Größe, die in dem verfestigten Produkt zudem unregelmäßig verteilt sind. Daraus resultieren eine schlechte Ausnutzung des Gebindevolumens und eine ungünstige Wirtschaftlichkeit.DE-PS 32 00 331 describes a process by which evaporator concentrates are dried in a heated repository vessel. Disadvantages of this process, however, are the relatively low evaporation rate and the formation of cavities, some of which are of considerable size, which are also distributed irregularly in the solidified product. This results in poor utilization of the container volume and an unfavorable economy.

In der DE-OS 3544270 wird ein Trocknungsverfahren beschrieben, bei dem zur Trocknung Mikrowellenenergie verwendet wird, wobei Flüssigkeiten und Lösungen in das Gebinde eingesprüht und in einem Schritt verfestigt werden. Dieses Verfahren ist sehr aufwendig und besitzt dadurch wirtschaftliche Nachteile.DE-OS 3544270 describes a drying process in which microwave energy is used for drying, liquids and solutions being sprayed into the container and solidified in one step. This process is very complex and therefore has economic disadvantages.

Es war daher Aufgabe der vorliegenden Erfindung, ein Verfahren zum Konditionieren von radioaktiven Verdampferlaugen, gegebenenfalls zusammen mit Kugelharzen, Kieselgur und Filterhilfsmitteln aus kerntechnischen Anlagen zum Zweck der endlagerfähigen Einschließung durch Eindampfen in beheizbaren Endlagergebinden zu schaffen, das eine hohe Raumausnutzung im Endlagergebinde, eine hohe Ausdampfleistung, und damit eine hohe Wirtschaftlichkeit gewährleistet.It was therefore an object of the present invention to provide a process for conditioning radioactive evaporator liquors, if appropriate together with spherical resins, diatomaceous earth and filter aids from nuclear plants for the purpose of confinement by disposal in evaporation in heatable repositories, which makes high use of space in the repository package, and has a high evaporation rate , and thus ensures a high level of economy.

Diese Aufgabe wird erfindungsgemäß dadurch gelöst, daß zunächst in einem Verdampfer die Lauge bzw. das Gemisch bis auf 60 bis etwa 85 Gew. % Trockensubstanzgehalt aufkonzentriert wird, dann das noch fließfähige Konzentrat in das beheizbare Endlagergebinde eingefüllt wird, und abschließend das Konzentrat im Endlagergebinde auf mindestens die im Endlager maximal auftretende Temperatur erhitzt und der dabei entstehende Dampf solange unter Unterdruck abgesaugt wird, bis sich ein fester Bodenkörper mit glatter Oberfläche ausgebildet hat.This object is achieved in that the liquor or the mixture is first concentrated to 60 to about 85% by weight dry matter content in an evaporator, then the still flowable concentrate is poured into the heatable final storage container, and finally the concentrate in the final storage container at least the maximum temperature occurring in the repository is heated and the steam produced is suctioned off under reduced pressure until a solid floor body with a smooth surface has formed.

Vorzugsweise wird das Konzentrat auf die im Endlager maximal auftretende Temperatur erhitzt.The concentrate is preferably heated to the maximum temperature occurring in the repository.

Weiterhin ist es vorteilhaft, das Konzentrat portionsweise in das Endlagergebinde einzufüllen und zu verfestigen. Dabei muß jede Teilportion erst verfestigt sein, bevor die nächste Teilportion eingefüllt wird.It is also advantageous to pour the concentrate into the final storage container in portions and to solidify it. Each portion must first be solidified before the next portion is filled.

Anhand der schematischen Abbildung soll das erfindungsgemäße Verfahren beispielhaft näher erläutert werden: Radioaktive Verdampferlauge (11), Kugelharze (12) und Filterhilfsmittel (13) aus Kernkraftwerken oder anderen kerntechnischen Anlagen werden in einen Verdampfer (1) gefördert, der mit einem Rührer (9), einem Tropfenabscheider (10), einem Kondensator (7) und einem Destillatsammelbehälter (8) versehen ist, von dem aus das Destillat kontrolliert entnommen werden kann. Im Verdampfer (1) wird das Gemisch (3) unter Rühren erhitzt und aufkonzentriert, bis das Konzentrat 60 bis etwa 85 Gew. % Trockensubstanz enthält. Das im bei der Verdampfertemperatur zähflüssigen und bei Raumtemperatur festen Konzentrat noch enthaltene Restwasser besteht im wesentlichen aus Kristallwasser des Salzanteils.The method according to the invention is to be explained in more detail by way of example with the aid of the schematic illustration: radioactive evaporator liquor (11), spherical resins (12) and filter aids (13) from nuclear power plants or other nuclear facilities are conveyed into an evaporator (1) which is operated with a stirrer (9) , a droplet separator (10), a condenser (7) and a distillate collector (8) is provided, from which the distillate can be removed in a controlled manner. In the evaporator (1), the mixture (3) is heated with stirring and concentrated until the concentrate contains 60 to about 85% by weight of dry substance. The residual water still present in the concentrate, which is viscous at the evaporator temperature and solid at room temperature, consists essentially of water of crystallization of the salt component.

Anschließend wird das zähflüssige Konzentrat portionsweise in ein mit Heizung (4) versehenes Endlagergebinde (2) abgelassen. Die erste Teilportion (5) wird durch Wärmezufuhr solange und so hoch erhitzt, daß der Kristallwassergehalt aus dem Konzentrat soweit ausgetrieben wird, daß sich im Endlagergebinde (2) ein fester monolithischer Bodenkörper mit glatter Oberfläche und ohne pulverförmige Anteile bildet. Dieser Bodenkörper muß auch bei der maximal im Endlager auftretenden Temperatur noch fest bleiben, sodaß die Eindampftemperatur im Endlagergebinde (2) mindestens so hoch sein muß wie die im Endlager maximal zu erwartende Temperatur. Man verwendet beispielsweise Eindampftemperaturen von etwa 70o C und saugt den entstehenden Dampf unter Unterdruck ab, wobei man bei diesem Eindampfprozess im Endlagergebinde (2) den Kondensator (7) und den Destillatsammelbehälter (8) des Verdampfers (1) mitbenutzen kann. Diese Mitbenutzung ist vor allem bei mobilen Anlagen von erheblichem wirtschaftlichen Vorteil. Nach der Verfestigung der ersten Teilportion (5) können weitere Teilportionen (6) des Konzentrats aus dem Verdampfer (1) in das Endlagergebinde (2) abgelassen und entsprechend verfestigt werden. Man erhält auf diese Weise ein Verfestigungsprodukt, das eine optimale Packungsdichte und Homogenität besitzt ohne das Zusatzstoffe erforderlich sind, die das Nutzvolumen des Endlagergebindes verringern würden. Das Verfestigungsprodukt weist nur noch einen Kristallwassergehalt von höchstens 10 Gew. % auf. Es werden hohe Packungsdichten erreicht, die je nach den zu verfestigenden Stoffen zwischen 1,2 und 1,6 kg/dm³ liegen können.The viscous concentrate is then discharged in portions into a final storage container (2) provided with a heater (4). The first portion (5) is heated by the supply of heat as long and so high that the crystal water content is expelled from the concentrate to such an extent that a solid monolithic soil body with a smooth surface and without powdery components forms in the final storage container (2). This floor must remain firm even at the maximum temperature occurring in the repository, so that the evaporation temperature in the repository package (2) must be at least as high as the maximum temperature to be expected in the repository. Evaporation temperatures of about 70 ° C. are used, for example, and the steam produced is drawn off under reduced pressure, with the condenser (7) and the distillate collecting container (8) of the evaporator (1) being able to be used in this evaporation process in the final storage container (2). This shared use is of considerable economic advantage, particularly in the case of mobile systems. After the first partial portion (5) has solidified, further partial portions (6) of the concentrate can be discharged from the evaporator (1) into the final storage container (2) and solidified accordingly. In this way, a solidification product is obtained which has an optimal packing density and homogeneity without the need for additives which would reduce the usable volume of the final storage container. The solidification product only has a crystal water content of at most 10% by weight. High packing densities are achieved, which can be between 1.2 and 1.6 kg / dm³ depending on the substances to be solidified.

Es ist auch möglich, die Verfestigung im Endlagergebinde nicht portionsweise, sondern auf einmal vorzunehmen, ohne daß die Qualität des verfestigten Endproduktes wesentlich schlechter ist. Auch läßt sich dieses zweistufige Konditionierungsverfahren automatisieren.It is also possible to carry out the solidification in the final storage container not in portions, but in one go, without the quality of the solidified end product being significantly poorer. This two-stage conditioning process can also be automated.

Folgendes Beispiel soll das erfindungsgemäße Verfahren näher erläutern:The following example is intended to explain the process according to the invention in more detail:

Ein Siedewasserreaktor-Simulatgemisch aus Verdampferlaugen, Ionenaustauscher-Kugelharzen und Filterhilfsmitteln wurde in einem Verdampfer zunächst aufkonzentriert. Das resultierende Konzentrat hatte die Zusammensetzung:
Na₂SO₄ 50 Gew. %
Kugelharze 15 Gew. %
Na₃PO₄ 5 Gew. %
Ca₃ (PO₄)₂ 1,5 Gew. %
Fe₂O₃ 1,5 Gew. %
Sonstiges 2,0 Gew. %
Restwasser 25 Gew. %
A boiling water reactor-simulate mixture of evaporator liquors, ion exchanger spherical resins and filter aids was first concentrated in an evaporator. The resulting concentrate had the composition:
Na₂SO₄ 50% by weight
Spherical resins 15% by weight
Na₃PO₄ 5% by weight
Ca₃ (PO₄) ₂ 1.5% by weight
Fe₂O₃ 1.5% by weight
Other 2.0% by weight
Residual water 25% by weight

Dieses Konzentrat wurde portionsweise in ein beheiztes Endlagergebinde abgelassen und bei 80o C bei 300 HPa verfestigt. Das Endprodukt wies einen Restwassergehalt von etwa 8 % auf und besaß ein mikroporöses Gefüge ohne Lunker und Inhomogenitäten. Die Endproduktoberfläche war glatt, die Abrieb- und Druckfestigkeit gut. Bei Beschleunigungstests änderte sich die geometrische Form nicht. Beheizungstests bei 70o C, die Endlagerungsbedingungen entsprechen, ergaben, daß das Verfestigungsprodukt seine Konsistenz nicht änderte.This concentrate was drained in portions into a heated repository and solidified at 80 o C at 300 HPa. The end product had a residual water content of about 8% and had a microporous structure without voids and inhomogeneities. The end product surface was smooth, the abrasion and pressure resistance good. The geometric shape did not change during acceleration tests. Heating tests at 70 o C, which correspond to final storage conditions, showed that the solidification product did not change its consistency.

Claims (3)

1. Verfahren zum Konditionieren von radioaktiven Verdampferlaugen, gegebenenfalls zusammen mit Kugelharzen, Kieselgur und Filterhilfsmitteln aus kerntechnischen Anlagen zum Zweck der endlagerfähigen Einschließung durch Eindampfen in beheizbaren Endlagergebinden,
dadurch gekennzeichnet,
daß zunächst in einem Verdampfer die Lauge, bzw. das Gemisch bis auf 60 bis etwa 85 Gew. % Trockensubstanzgehalt aufkonzentriert wird, dann das noch fließfähige Konzentrat in das beheizbare Endlagergebinde eingefüllt wird, und abschließend das Konzentrat im Endlagergebinde auf mindestens die im Endlager maximal auftretende Temperatur erhitzt, und der dabei entstehende Dampf solange unter Unterdruck abgesaugt wird, bis sich ein fester Bodenkörper mit glatter Oberfläche ausgebildet hat.
1. A method for conditioning radioactive evaporator liquors, if appropriate together with spherical resins, diatomaceous earth and filter aids from nuclear facilities for the purpose of containment by disposal by evaporation in heatable final storage containers,
characterized,
that the liquor or the mixture is first concentrated to 60 to about 85% by weight dry matter content in an evaporator, then the still flowable concentrate is poured into the heatable final storage container, and finally the concentrate in the final storage container to at least the maximum occurring in the final storage Temperature heated, and the resulting steam is sucked off under vacuum until a solid floor body with a smooth surface has formed.
2. Verfahren nach Anspruch 1,
dadurch gekennzeichnet,
daß das Konzentrat im Endlagergebinde auf die maximal im Endlager auftretende Temperatur erhitzt wird.
2. The method according to claim 1,
characterized,
that the concentrate in the repository is heated to the maximum temperature occurring in the repository.
3. Verfahren nach Anspruch 1 und 2,
dadurch gekennzeichnet,
daß das Konzentrat portionsweise in das Endlagergebinde eingefüllt und verfestigt wird.
3. The method according to claim 1 and 2,
characterized,
that the concentrate is poured into the final storage container in portions and solidified.
EP19890114316 1988-08-17 1989-08-03 Process for conditioning radioactive evaporator concentrates form nuclear plants Withdrawn EP0355514A3 (en)

Applications Claiming Priority (2)

Application Number Priority Date Filing Date Title
DE19883827897 DE3827897A1 (en) 1988-08-17 1988-08-17 METHOD FOR CONDITIONING RADIOACTIVE EVAPORATOR LIQUIDS FROM NUCLEAR FACILITIES
DE3827897 1988-08-17

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EP0355514A2 true EP0355514A2 (en) 1990-02-28
EP0355514A3 EP0355514A3 (en) 1991-12-27

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Cited By (3)

* Cited by examiner, † Cited by third party
Publication number Priority date Publication date Assignee Title
WO1995026556A1 (en) * 1994-03-25 1995-10-05 British Nuclear Fuels Plc Drying wet radioactive, toxic or other hazardous waste
ES2184540A1 (en) * 1999-10-26 2003-04-01 Equipos Nucleares Sa Radioactive liquid waste treatment and storage system comprises continuous inputter with desiccation chamber and concrete shield
EP2733704A3 (en) * 2012-11-16 2016-06-29 Hartmut Grunau Final storage container and method for drying contaminated objects in a final storage container and method for the production of same

Families Citing this family (1)

* Cited by examiner, † Cited by third party
Publication number Priority date Publication date Assignee Title
DE19913103C1 (en) * 1999-03-23 2000-12-14 Kernkraftwerke Gundremmingen B Decontamination of radioactive vaporizer concentrate comprises freeing it of undissolved components, crystallizing out sodium sulfate as the decahydrate, and returning the concentrate to the system

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DE1614497A1 (en) * 1967-04-12 1970-08-20 Siemens Ag Process for the concentration of radioactive waste
FR2307342A1 (en) * 1975-04-11 1976-11-05 Licentia Gmbh RADIOACTIVE CONCENTRATE TREATMENT PROCESS
GB2113902A (en) * 1982-01-08 1983-08-10 Nuklear Service Gmbh Gns Process and apparatus for treating moist radioactive wastes
GB2163894A (en) * 1984-08-16 1986-03-05 Nuklear Service Gmbh Gns Preparing radioactive waste solids and evaporator concentrates for final storage in permanent storage containers
DE3432103A1 (en) * 1984-08-31 1986-03-13 Kraftwerk Union AG, 4330 Mülheim Method of reducing the volume of radioactively charged liquids and ribbed body for use thereby

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DE1088624B (en) * 1959-06-27 1960-09-08 Ver Kesselwerke Ag Method and device for removing radioactive contaminants from liquids, in particular from water, by evaporation
DE3029147A1 (en) * 1980-07-31 1982-02-25 Kraftwerk Union AG, 4330 Mülheim Treatment of radioactive residue of waste liquor contg. borate - by adjusting sodium boron molar ratio during concn. by evapn.

Patent Citations (5)

* Cited by examiner, † Cited by third party
Publication number Priority date Publication date Assignee Title
DE1614497A1 (en) * 1967-04-12 1970-08-20 Siemens Ag Process for the concentration of radioactive waste
FR2307342A1 (en) * 1975-04-11 1976-11-05 Licentia Gmbh RADIOACTIVE CONCENTRATE TREATMENT PROCESS
GB2113902A (en) * 1982-01-08 1983-08-10 Nuklear Service Gmbh Gns Process and apparatus for treating moist radioactive wastes
GB2163894A (en) * 1984-08-16 1986-03-05 Nuklear Service Gmbh Gns Preparing radioactive waste solids and evaporator concentrates for final storage in permanent storage containers
DE3432103A1 (en) * 1984-08-31 1986-03-13 Kraftwerk Union AG, 4330 Mülheim Method of reducing the volume of radioactively charged liquids and ribbed body for use thereby

Cited By (4)

* Cited by examiner, † Cited by third party
Publication number Priority date Publication date Assignee Title
WO1995026556A1 (en) * 1994-03-25 1995-10-05 British Nuclear Fuels Plc Drying wet radioactive, toxic or other hazardous waste
ES2184540A1 (en) * 1999-10-26 2003-04-01 Equipos Nucleares Sa Radioactive liquid waste treatment and storage system comprises continuous inputter with desiccation chamber and concrete shield
EP2733704A3 (en) * 2012-11-16 2016-06-29 Hartmut Grunau Final storage container and method for drying contaminated objects in a final storage container and method for the production of same
EP3203482A1 (en) * 2012-11-16 2017-08-09 Hartmut Grunau Final storage container and method for drying contaminated objects in a final storage container

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DE3827897C2 (en) 1992-07-30
DE3827897A1 (en) 1990-03-22
EP0355514A3 (en) 1991-12-27

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