EP0037324A1 - Process for immobilizing radioactive alcaline or earth alcaline elements - Google Patents
Process for immobilizing radioactive alcaline or earth alcaline elements Download PDFInfo
- Publication number
- EP0037324A1 EP0037324A1 EP81400467A EP81400467A EP0037324A1 EP 0037324 A1 EP0037324 A1 EP 0037324A1 EP 81400467 A EP81400467 A EP 81400467A EP 81400467 A EP81400467 A EP 81400467A EP 0037324 A1 EP0037324 A1 EP 0037324A1
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- EP
- European Patent Office
- Prior art keywords
- slag
- waste
- silico
- fine
- radioactive
- 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.)
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- 238000000034 method Methods 0.000 title claims description 13
- 230000002285 radioactive effect Effects 0.000 title claims description 13
- 230000003100 immobilizing effect Effects 0.000 title 1
- 239000002893 slag Substances 0.000 claims abstract description 32
- 239000004567 concrete Substances 0.000 claims abstract description 20
- 239000002699 waste material Substances 0.000 claims abstract description 19
- 239000000463 material Substances 0.000 claims abstract description 7
- 239000011440 grout Substances 0.000 claims abstract description 4
- 239000004576 sand Substances 0.000 claims abstract description 3
- 239000003054 catalyst Substances 0.000 claims abstract 4
- 239000000203 mixture Substances 0.000 claims description 7
- 238000004519 manufacturing process Methods 0.000 claims description 6
- 230000000903 blocking effect Effects 0.000 claims description 4
- 239000004568 cement Substances 0.000 claims description 4
- 239000002901 radioactive waste Substances 0.000 claims description 3
- 229910001021 Ferroalloy Inorganic materials 0.000 claims description 2
- OAICVXFJPJFONN-UHFFFAOYSA-N Phosphorus Chemical compound [P] OAICVXFJPJFONN-UHFFFAOYSA-N 0.000 claims description 2
- 239000011248 coating agent Substances 0.000 claims description 2
- 238000000576 coating method Methods 0.000 claims description 2
- 239000010881 fly ash Substances 0.000 claims description 2
- 239000002245 particle Substances 0.000 claims description 2
- 229910052698 phosphorus Inorganic materials 0.000 claims description 2
- 239000011574 phosphorus Substances 0.000 claims description 2
- 238000003860 storage Methods 0.000 claims description 2
- -1 ferrous metals Chemical class 0.000 claims 1
- 229910052751 metal Inorganic materials 0.000 claims 1
- 239000002184 metal Substances 0.000 claims 1
- 229910052752 metalloid Inorganic materials 0.000 claims 1
- 150000002738 metalloids Chemical class 0.000 claims 1
- 238000005272 metallurgy Methods 0.000 claims 1
- CIOAGBVUUVVLOB-NJFSPNSNSA-N Strontium-90 Chemical compound [90Sr] CIOAGBVUUVVLOB-NJFSPNSNSA-N 0.000 abstract description 8
- 239000003513 alkali Substances 0.000 abstract description 2
- TVFDJXOCXUVLDH-RNFDNDRNSA-N cesium-137 Chemical compound [137Cs] TVFDJXOCXUVLDH-RNFDNDRNSA-N 0.000 description 6
- XLYOFNOQVPJJNP-UHFFFAOYSA-N water Substances O XLYOFNOQVPJJNP-UHFFFAOYSA-N 0.000 description 6
- 150000002500 ions Chemical class 0.000 description 4
- 239000003643 water by type Substances 0.000 description 4
- 239000012190 activator Substances 0.000 description 3
- 235000008733 Citrus aurantifolia Nutrition 0.000 description 2
- 235000011941 Tilia x europaea Nutrition 0.000 description 2
- 230000004888 barrier function Effects 0.000 description 2
- 150000001875 compounds Chemical class 0.000 description 2
- 238000009792 diffusion process Methods 0.000 description 2
- 230000000694 effects Effects 0.000 description 2
- 239000004571 lime Substances 0.000 description 2
- 230000005012 migration Effects 0.000 description 2
- 238000013508 migration Methods 0.000 description 2
- 230000005855 radiation Effects 0.000 description 2
- 239000013535 sea water Substances 0.000 description 2
- 239000002002 slurry Substances 0.000 description 2
- OYEHPCDNVJXUIW-FTXFMUIASA-N 239Pu Chemical compound [239Pu] OYEHPCDNVJXUIW-FTXFMUIASA-N 0.000 description 1
- RYGMFSIKBFXOCR-UHFFFAOYSA-N Copper Chemical compound [Cu] RYGMFSIKBFXOCR-UHFFFAOYSA-N 0.000 description 1
- 241001508691 Martes zibellina Species 0.000 description 1
- 239000011398 Portland cement Substances 0.000 description 1
- IGLNJRXAVVLDKE-OUBTZVSYSA-N Rubidium-86 Chemical compound [86Rb] IGLNJRXAVVLDKE-OUBTZVSYSA-N 0.000 description 1
- 229910000720 Silicomanganese Inorganic materials 0.000 description 1
- 239000002253 acid Substances 0.000 description 1
- 230000016571 aggressive behavior Effects 0.000 description 1
- 150000001447 alkali salts Chemical class 0.000 description 1
- 229910052782 aluminium Inorganic materials 0.000 description 1
- PNEYBMLMFCGWSK-UHFFFAOYSA-N aluminium oxide Inorganic materials [O-2].[O-2].[O-2].[Al+3].[Al+3] PNEYBMLMFCGWSK-UHFFFAOYSA-N 0.000 description 1
- 230000015572 biosynthetic process Effects 0.000 description 1
- 229910052792 caesium Inorganic materials 0.000 description 1
- TVFDJXOCXUVLDH-UHFFFAOYSA-N caesium atom Chemical compound [Cs] TVFDJXOCXUVLDH-UHFFFAOYSA-N 0.000 description 1
- 230000015556 catabolic process Effects 0.000 description 1
- ZCDOYSPFYFSLEW-UHFFFAOYSA-N chromate(2-) Chemical compound [O-][Cr]([O-])(=O)=O ZCDOYSPFYFSLEW-UHFFFAOYSA-N 0.000 description 1
- 229910052804 chromium Inorganic materials 0.000 description 1
- 239000011651 chromium Substances 0.000 description 1
- 230000006835 compression Effects 0.000 description 1
- 238000007906 compression Methods 0.000 description 1
- 229910052802 copper Inorganic materials 0.000 description 1
- 239000010949 copper Substances 0.000 description 1
- 238000005336 cracking Methods 0.000 description 1
- 235000013365 dairy product Nutrition 0.000 description 1
- 230000006378 damage Effects 0.000 description 1
- 238000006731 degradation reaction Methods 0.000 description 1
- 238000006073 displacement reaction Methods 0.000 description 1
- 238000004090 dissolution Methods 0.000 description 1
- 239000012530 fluid Substances 0.000 description 1
- 239000000446 fuel Substances 0.000 description 1
- 230000036571 hydration Effects 0.000 description 1
- 238000006703 hydration reaction Methods 0.000 description 1
- 238000002386 leaching Methods 0.000 description 1
- JQJCSZOEVBFDKO-UHFFFAOYSA-N lead zinc Chemical compound [Zn].[Pb] JQJCSZOEVBFDKO-UHFFFAOYSA-N 0.000 description 1
- LBSANEJBGMCTBH-UHFFFAOYSA-N manganate Chemical compound [O-][Mn]([O-])(=O)=O LBSANEJBGMCTBH-UHFFFAOYSA-N 0.000 description 1
- 239000008267 milk Substances 0.000 description 1
- 235000013336 milk Nutrition 0.000 description 1
- 210000004080 milk Anatomy 0.000 description 1
- 239000004570 mortar (masonry) Substances 0.000 description 1
- 239000003758 nuclear fuel Substances 0.000 description 1
- 238000004806 packaging method and process Methods 0.000 description 1
- 238000011084 recovery Methods 0.000 description 1
- 238000007670 refining Methods 0.000 description 1
- 238000012958 reprocessing Methods 0.000 description 1
- 150000003839 salts Chemical class 0.000 description 1
- 150000004760 silicates Chemical class 0.000 description 1
- 239000010802 sludge Substances 0.000 description 1
- 239000007787 solid Substances 0.000 description 1
- 238000005063 solubilization Methods 0.000 description 1
- 230000007928 solubilization Effects 0.000 description 1
- 238000001179 sorption measurement Methods 0.000 description 1
- 230000008961 swelling Effects 0.000 description 1
- NWONKYPBYAMBJT-UHFFFAOYSA-L zinc sulfate Chemical compound [Zn+2].[O-]S([O-])(=O)=O NWONKYPBYAMBJT-UHFFFAOYSA-L 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
-
- 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
- G21F9/30—Processing
- G21F9/301—Processing by fixation in stable solid media
- G21F9/302—Processing by fixation in stable solid media in an inorganic matrix
Definitions
- the present invention relates to the field of protection against radioactivity of materials, materials, contaminated objects or waste of any kind in general.
- the invention provides a solution to the problem of preserving waste containing Cesium 137, Strontium 90 and other long-lived elements by providing a means of packaging for solid residues or solutions previously solidified by an appropriate means described in the application. Patent No. 79.07246 of the Applicant.
- the process of the invention essentially consists in blocking the waste, introduced into containers of concrete or other material, using metallurgical slag with a glassy structure and finely ground.
- slag with a particle size less than 2 mm, preferably ground to less than 0.1 mm and having a specific surface greater than 1500 cm 2 / g (measured according to the Blaine method).
- the waste When the waste is coated in a slag slurry, the latter prevents the diffusion of radioactive elements.
- the hypotheses put forward concerning the zeolitic effect of the silico-aluminum slags there exist in the network of free sites in which the alkaline and alkaline-earth ions are preferably housed, but also other ions (chromate , manganate zincate, etc.) which are also insolubilized, and the release of insoluble, precipitated and adsorbed adsorbed ions is extremely low.
- slag and sqories are suitable for carrying out the process of the invention.
Landscapes
- Engineering & Computer Science (AREA)
- Physics & Mathematics (AREA)
- General Engineering & Computer Science (AREA)
- High Energy & Nuclear Physics (AREA)
- Chemical & Material Sciences (AREA)
- Inorganic Chemistry (AREA)
- Environmental & Geological Engineering (AREA)
- Processing Of Solid Wastes (AREA)
- Solid-Sorbent Or Filter-Aiding Compositions (AREA)
Abstract
Description
La présente invention a trait au domaine de la protection contre la radioactivité de matières, matériaux, objets contaminés ou déchets de toute nature en général.The present invention relates to the field of protection against radioactivity of materials, materials, contaminated objects or waste of any kind in general.
On sait qu'au cours de la fabrication de combustibles nucléaires, de leur utilisation en réacteur, du retraitement des combustibles usagés, il se produit des résidus et des déchets présentant divers degrés de radioactivité. Des matériaux irradiés, des engins ou des outils, des vêtements ou d'autres objets contaminés doivent être également considérés comme des déchets radioactifs. Les boues et les solutions radioctives sont également des résidus qu'il est nécessaire de traiter avant tout stockage définitif.It is known that during the production of nuclear fuels, their use in reactors, the reprocessing of used fuels, residues and waste with various degrees of radioactivity are produced. Irradiated materials, machinery or tools, clothing or other contaminated objects should also be considered as radioactive waste. Sludge and radioactive solutions are also residues that must be treated before final disposal.
Habituellement, les résidus et déchets en tout genre sont mis en fûts sur les lieux de leur production et sont ensuite expédiés vers les lieux de stockage définitifs. Le plus souvent,on utilise pour les résidus moyennement ou faiblement radioactifs des récipients en bétons présentant les caractéristiques mécaniques appropriées, telles que résistance à la compression, à la traction ou à la fissuration, aux chocs, etc.. On a cependant constaté que les récipients en béton, s'ils présentent toujours des caractéristiques mécaniques suffisantes, ne présentent pas une pérennité absolue vis à vis de l'action agressive des milieux où doivent être stockés les récipients en béton.Usually, residues and waste of all kinds are put in barrels at the place of their production and are then sent to the final storage places. Most often, for the medium or weakly radioactive residues, use is made of concrete containers having the appropriate mechanical characteristics, such as resistance to compression, traction or cracking, impact, etc. It has however been found that the concrete containers, if they still have sufficient mechanical characteristics, do not have absolute durability with respect to the aggressive action of the environments in which the concrete containers must be stored.
Ainsi, il est bien connu que les bétons ne résistent pas parfaitement à l'action de l'eau de mer, de certaines eaux minéralisées (eaux séléniteuses par exemple) ou d'eaux trop pures. Il se produit alors une destruction progressive de l'enveloppe en béton par l'action des sels dissous qui pénètrent dans le réseau des silicates hydratés en provoquant le gonflement puis la désagrégation du béton. De même, les bétons fabriqués à partir de Ciment Portland Artificiel contiennent toujours un peu de chaux libre. Celle-ci est fortement dissoute par l'eau pure et on observe lephénomène dénommé lixiviation.Thus, it is well known that concretes do not fully resist the action of seawater, certain mineralized waters (selenitic waters for example) or excessively pure waters. It then occurs a gradual destruction of the concrete shell by the action of dissolved salts which penetrate into the network of hydrated silicates causing the swelling then the disintegration of the concrete. Likewise, concretes made from Artificial Portland Cement always contain a little free lime. This is strongly dissolved by pure water and we observe the phenomenon called leaching.
Ceci explique pourquoi les récipients en béton à base de CPA ne présentent pas toutes les garanties de pérennité et n'assurent pas un confinement parfait des déchets contenant des éléments radioactifs des groupes alcalins et alcalino-terreux. Ces éléments ont des périodes plus ou moins longues ; lorsque celles-ci ne dépassent pas plusieurs jours ou même quelques mois, le problème ne se pose pas. Par contre, lorsque la période est plus importante, les récipients en béton à base de CPA ne sont plus suffisants.This explains why concrete containers based on CPA do not offer all the guarantees of durability and do not ensure perfect containment of waste containing radioactive elements of alkaline and alkaline-earth groups. These elements have more or less long periods; when these do not exceed several days or even a few months, the problem does not arise. On the other hand, when the period is longer, concrete containers based on CPA are no longer sufficient.
Parmi les éléments radioactifs possédant un pouvoir de migration important dû à la solubilisation par l'eau du béton et au déplacement des ions dans ce béton, ainsi qu'une période assez longue pour pouvoir migrer de la face intérieure de l'enveloppe en béton, il faut citer principalement :
- . le Strontium 90 de période 28,8 ans (rayonnement béta)
- . le Césium 137 de période 30 ans (rayonnement béta)
- . Strontium 90 with a 28.8-year period (beta radiation)
- . Cesium 137 with a 30-year period (beta radiation)
Ce dernier faisant partie du groupe des alcalins, ses composés sont particulièrement solubles et la masse correspondant à une activité de 1 curie est de 11,5 mg ; pour le Strontium 90, la masse équivalente est de 7,05 mg. On peut également joindre à ces deux éléments le Rubidium 86 qui se trouve dans le groupe des alcalins de radioactivité modérée. Le Plutonium 239 pose un problème par suite de sa longue période (24.300 ans), ce qui nécessite des récipients de longévité pratiquement sans commune mesure avec celle des récipients destinés à conserver des déchets contenant du Césium 137 et du Strontium 90.The latter being part of the alkali group, its compounds are particularly soluble and the mass corresponding to an activity of 1 curie is 11.5 mg; for Strontium 90, the equivalent mass is 7.05 mg. We can also join these two elements Rubidium 86 which is in the group of alkalines of moderate radioactivity. Plutonium 239 poses a problem due to its long period (24,300 years), which requires containers with longevity practically incommensurate with that of containers intended to store waste containing Cesium 137 and Strontium 90.
L'invention apporte une solution au problème de la conservation des déchets contenant du Césium 137, du Strontium 90 et autres éléments de longue période en offrant un moyen de conditionnement pour des résidus solides ou de solutions préalablement solidifiées par un moyen approprié décrit dans la demande de brevet n°79.07246 de la Demanderesse.The invention provides a solution to the problem of preserving waste containing Cesium 137, Strontium 90 and other long-lived elements by providing a means of packaging for solid residues or solutions previously solidified by an appropriate means described in the application. Patent No. 79.07246 of the Applicant.
Le procédé de l'invention consiste essentiellement à bloquer les déchets, introduits dans des récipients en béton ou autre matériau, à l'aide de laitier métallurgique de structure vitreuse et broyé finement.The process of the invention essentially consists in blocking the waste, introduced into containers of concrete or other material, using metallurgical slag with a glassy structure and finely ground.
Ce laitier peut être utilisé sous deux formes :
- - soit sous forme de coulis de grande fluidité qui comble tous les vides subsistant entre les déchets. Pour que le coulis de laitier fasse prise, il est nécessaire qu'il contienne un activateur de prise (clinker broyé, chaux, ou sels d'alcalins). Après prise et durcissement, les déchets sont maintenus en place et on ferme hermétiquement le récipient ;
- - soit sous forme de sable fin sec additionné d'un activant de prise également anhydre. Le récipient rempli est vibré afin que le mélange puisse combler tous les vides pour que les déchets soient parfaitement enveloppés ; on procède ensuite à la fermeture du récipient.
- - either in the form of a highly fluid grout which fills all the gaps remaining between the waste. In order for the slag coulis to set, it must contain a setting activator (crushed clinker, lime, or alkali salts). After setting and hardening, the waste is kept in place and the container is hermetically closed;
- - either in the form of dry fine sand added with a setting anhydrous also. The filled container is vibrated so that the mixture can fill all the gaps so that the waste is perfectly wrapped; the container is then closed.
Selon une variante de réalisation, on peut utiliser en premier lieu le coulis à base de laitier jusqu'à recouvrement des déchets puis rajouter le mélange de laitier fin sec additionné de l'activateur de prise et procéder ensuite à la fermeture du récipient.According to an alternative embodiment, it is possible to use first the slurry based on slag until recovery of the waste then add the mixture of dry slag added with the setting activator and then proceed to close the container.
Pour réaliser ces opérations, il est préconisé d'utiliser du laitier de granulométrie inférieure à 2 mm, de préférence broyé à moins de 0,1 mm et présentant une surface spécifique supérieure à 1500 cm2/g (mesurée suivant la méthode de Blaine).To carry out these operations, it is recommended to use slag with a particle size less than 2 mm, preferably ground to less than 0.1 mm and having a specific surface greater than 1500 cm 2 / g (measured according to the Blaine method).
Cette façon d'opérer empêche la diffusion des éléments radioactifs hors du récipient du fait que les laitiers métallurgiques possèdent des propriétés zéolithiques qui leur permettent de capter et de retenir les éléments radioactifs (le Césium 137 et le Strontium 90) dont les composés ont un pouvoir de dissolution leur permettant de migrer à travers des barrières ne possédant pas ces propriétés zéolithiques.This way of operating prevents the diffusion of radioactive elements out of the container because metallurgical slags have zeolitic properties which allow them to capture and retain radioactive elements (Cesium 137 and Strontium 90) whose compounds have a power of dissolution allowing them to migrate through barriers not possessing these zeolitic properties.
Lorsqu'on enrobe les déchets dans un coulis de laitier, ce dernier empêche la diffusion des éléments radioactifs. Selon les hypothèses émises au sujet de l'effet zéolithique des laitiers silico-alumi- natés, il existe dans le réseau des sites libres dans lesquels viennent se loger de préférence les ions alcalins et alcalino-terreux, mais aussi d'autres ions (chromate, zincate manganaté, etc..) qui sont aussiinsolubi- lisés, et le relargage des ions adsorbés insolubilisés, précipités et adsorbés est extrêmement faible.When the waste is coated in a slag slurry, the latter prevents the diffusion of radioactive elements. According to the hypotheses put forward concerning the zeolitic effect of the silico-aluminum slags, there exist in the network of free sites in which the alkaline and alkaline-earth ions are preferably housed, but also other ions (chromate , manganate zincate, etc.) which are also insolubilized, and the release of insoluble, precipitated and adsorbed adsorbed ions is extremely low.
On a pu déterminer expérimentalement que certains laitiers broyés fins pouvaient fixer au moins 15 mg de Césium par 100 g de laitier, ce qui est considérable puisque Il,5 mg de Césium 137 correspondent à une radioactivité de 1 curie.We have been able to determine experimentally that certain fine ground slag could fix at least 15 mg of Cesium per 100 g of slag, which is considerable since II.5 mg of Cesium 137 correspond to a radioactivity of 1 curie.
Dans le cas d'un enrobage à sec des déchets par un mélange de laitier fin additionné d'activant anhydre, la fixation des éléments nocifs se fait plus lentement. Dans le cas d'une dégradation de l'enveloppe extérieure, l'eau qui pourrait s'introduire dans le récipient prove- querait l'hydratation du laitier activé et on aurait la formation d'un mortier qui par suite de sa prise consoliderait le récipient tout en conservant ses propriétés d'adsorption des éléments radioactifs,In the case of dry coating of the waste with a mixture of fine slag added with anhydrous activator, the fixing of the harmful elements takes place more slowly. In the event of degradation of the outer envelope, the water which could be introduced into the container would cause the hydration of the activated slag and there would be the formation of a mortar which, as a result of its setting, would consolidate the container while retaining its adsorption properties of radioactive elements,
On peut utiliser soit du laitier silico-alumineux seul, soit en mélange avec des cendres volantes de centrales thermiques, soit avec des pouzzolanes naturelles ou artificielles.One can use either silico-aluminous slag alone, or in a mixture with fly ash from thermal power stations, or with natural or artificial pozzolans.
Enfin, comme les bétons confectionnés à partir de ciment CPA ne présentent pas les garanties suffisantes de pérennité par suite des phénomènes d'agression des eaux, on a grand intérêt a fabriquer des récipients en béton de granulats de laitier en utilisant comme liants des ciments à haute teneur en laitier (CLK ou CHF). Il a en effet été démontré dans le cadre des travaux de l'invention, que les bétons tout laitier présentent une grande résistance aux eaux agressives (eau de mer, eaux sulfatées, eaux acides) et forment une barrière qui possède des propriétés zéolithiques donc empêchant la migration des éléments radioactifs. Il est donc recommandé de prévoir des récipients en béton tout laitier pour contenir des déchets chargés de Césium 137, de Strontium 90 ou autres éléments radioactifs de longue période.Finally, as concretes made from CPA cement do not offer sufficient guarantees of durability as a result of water aggression phenomena, it is of great interest to manufacture concrete containers from slag aggregates using cement cements to high milk content (CLK or CHF). It has indeed been demonstrated in the context of the work of the invention, that all dairy concretes have a high resistance to aggressive waters (sea water, sulphated water, acid water) and form a barrier which has zeolitic properties therefore preventing the migration of radioactive elements. It is therefore recommended to provide all-dairy concrete containers to contain waste loaded with Cesium 137, Strontium 90 or other long-lived radioactive elements.
La plupart des laitiers et sqories conviennent pour la mise en oeuvre du procédé de l'invention. Parmi les plus aptes, il faut classer ceux qui contiennent une proportion notable d'alumine, car ce sont essentiellement les silico-aluminates qui présentent des propriétés zéolithiques. On peut recommander d'utiliser principalement les laitiers de haut fourneau, de fonderie, les laitiers provenant de la fabrication des ferro-alliages principalement clu silico-chrome, du silico-manganèse, des fours plomb-zinc, de l'affinage du Cuivre et de la fabrication du phosphore.Most slag and sqories are suitable for carrying out the process of the invention. Among the most suitable, it is necessary to classify those which contain a significant proportion of alumina, since it is essentially the silico-aluminates which exhibit zeolitic properties. We can recommend using mainly blast furnace slag, foundry slag, slag from the manufacture of ferro-alloys mainly clu silico-chromium, silico-manganese, lead-zinc furnaces, copper refining and of phosphorus production.
Claims (7)
Applications Claiming Priority (2)
| Application Number | Priority Date | Filing Date | Title |
|---|---|---|---|
| FR8006806A FR2479541A1 (en) | 1980-03-27 | 1980-03-27 | METHOD FOR BLOCKING ALKALI AND ALKALINE-EARTH RADIO-ACTIVE ELEMENTS |
| FR8006806 | 1980-03-27 |
Publications (1)
| Publication Number | Publication Date |
|---|---|
| EP0037324A1 true EP0037324A1 (en) | 1981-10-07 |
Family
ID=9240171
Family Applications (1)
| Application Number | Title | Priority Date | Filing Date |
|---|---|---|---|
| EP81400467A Withdrawn EP0037324A1 (en) | 1980-03-27 | 1981-03-25 | Process for immobilizing radioactive alcaline or earth alcaline elements |
Country Status (4)
| Country | Link |
|---|---|
| EP (1) | EP0037324A1 (en) |
| JP (1) | JPS56151399A (en) |
| FR (1) | FR2479541A1 (en) |
| ZA (1) | ZA811602B (en) |
Cited By (9)
| Publication number | Priority date | Publication date | Assignee | Title |
|---|---|---|---|---|
| FR2527376A1 (en) * | 1982-05-21 | 1983-11-25 | Kernforschungsz Karlsruhe | PROCESS FOR IMPROVING THE PROPERTIES OF RADIOACTIVE SOLID WASTE INCORPORATED IN A MATRIX AND SOLIDIFIED |
| WO1984000841A1 (en) * | 1982-08-16 | 1984-03-01 | Litovitz Theodore A | Fixation of anionic materials with a complexing agent |
| EP0297356A1 (en) * | 1987-07-03 | 1989-01-04 | Siemens Aktiengesellschaft | Waste container, particularly for final deposit of radioactive substances |
| US5198128A (en) * | 1987-07-03 | 1993-03-30 | Siemens Aktiengesellschaft | Waste disposal site, in particular for the ultimate disposal of radioactive substances |
| EP0709859A1 (en) * | 1994-10-27 | 1996-05-01 | Jgc Corporation | Solidifying material for radioactive wastes, process for solidifying radioactive wastes and solidified product |
| US5732363A (en) * | 1994-10-27 | 1998-03-24 | Jgc Corporation | Solidifying material for radioactive wastes, process for solidifying radioactive wastes and solidified product |
| RU2122754C1 (en) * | 1997-10-21 | 1998-11-27 | Производственное объединение "МАЯК" | Composition based on natural and artificial aluminosilicate materials for hardening liquid low- and medium-activity wastes with high concentration of sodium salts, among which is radioactive cesium |
| FR2844913A1 (en) * | 2002-09-20 | 2004-03-26 | Univ Pasteur | PROCESS FOR CONTAINING CESIUM AND / OR RUBIDIUM IN SINTERED CERAMIC MATRICES BASED ON EXPANDED PERLITE, MATRICES USED AND PRODUCTS THUS OBTAINED. |
| RU2375773C1 (en) * | 2008-03-03 | 2009-12-10 | Федеральное государственное унитарное предприятие "Производственное объединение "Маяк" | Composition for cementing liquid radioactive wastes |
Families Citing this family (3)
| Publication number | Priority date | Publication date | Assignee | Title |
|---|---|---|---|---|
| JPS61274299A (en) * | 1985-05-30 | 1986-12-04 | 三菱重工業株式会社 | Solidification of radioactive waste |
| JP2002243892A (en) * | 2001-02-22 | 2002-08-28 | Hitachi Ltd | Solidification method for radioactive alkaline waste liquid |
| JP5661066B2 (en) * | 2012-05-28 | 2015-01-28 | 株式会社 フュー・テクノロジー | Method for treating incinerated ash containing radioactive material and treated solids |
Citations (3)
| Publication number | Priority date | Publication date | Assignee | Title |
|---|---|---|---|---|
| DE2717656A1 (en) * | 1977-04-21 | 1978-10-26 | Nukem Gmbh | PROCESS FOR THE PRODUCTION OF LEAK-RESISTANT AND SALINE-RESISTANT BLOCKS FROM CEMENT AND RADIOACTIVE WASTE |
| FR2395573A1 (en) * | 1977-06-24 | 1979-01-19 | Pechiney Ugine Kuhlmann Uran | PROCESS FOR PACKAGING FISSION PRODUCTS FROM THE TREATMENT OF IRRADIED FUELS BY DRY METHOD |
| FR2432752A1 (en) * | 1978-08-03 | 1980-02-29 | Gagneraud Francis | PROCESS FOR COATING RADIOACTIVE WASTE TO PROVIDE SAFE TRANSPORT AND STORAGE |
-
1980
- 1980-03-27 FR FR8006806A patent/FR2479541A1/en active Granted
-
1981
- 1981-03-11 ZA ZA00811602A patent/ZA811602B/en unknown
- 1981-03-25 EP EP81400467A patent/EP0037324A1/en not_active Withdrawn
- 1981-03-26 JP JP4465181A patent/JPS56151399A/en active Pending
Patent Citations (3)
| Publication number | Priority date | Publication date | Assignee | Title |
|---|---|---|---|---|
| DE2717656A1 (en) * | 1977-04-21 | 1978-10-26 | Nukem Gmbh | PROCESS FOR THE PRODUCTION OF LEAK-RESISTANT AND SALINE-RESISTANT BLOCKS FROM CEMENT AND RADIOACTIVE WASTE |
| FR2395573A1 (en) * | 1977-06-24 | 1979-01-19 | Pechiney Ugine Kuhlmann Uran | PROCESS FOR PACKAGING FISSION PRODUCTS FROM THE TREATMENT OF IRRADIED FUELS BY DRY METHOD |
| FR2432752A1 (en) * | 1978-08-03 | 1980-02-29 | Gagneraud Francis | PROCESS FOR COATING RADIOACTIVE WASTE TO PROVIDE SAFE TRANSPORT AND STORAGE |
Cited By (11)
| Publication number | Priority date | Publication date | Assignee | Title |
|---|---|---|---|---|
| FR2527376A1 (en) * | 1982-05-21 | 1983-11-25 | Kernforschungsz Karlsruhe | PROCESS FOR IMPROVING THE PROPERTIES OF RADIOACTIVE SOLID WASTE INCORPORATED IN A MATRIX AND SOLIDIFIED |
| GB2124015A (en) * | 1982-05-21 | 1984-02-08 | Kernforschungsz Karlsruhe | Method for improving the properties of solidified radioactive solid wastes |
| WO1984000841A1 (en) * | 1982-08-16 | 1984-03-01 | Litovitz Theodore A | Fixation of anionic materials with a complexing agent |
| EP0297356A1 (en) * | 1987-07-03 | 1989-01-04 | Siemens Aktiengesellschaft | Waste container, particularly for final deposit of radioactive substances |
| US5198128A (en) * | 1987-07-03 | 1993-03-30 | Siemens Aktiengesellschaft | Waste disposal site, in particular for the ultimate disposal of radioactive substances |
| EP0709859A1 (en) * | 1994-10-27 | 1996-05-01 | Jgc Corporation | Solidifying material for radioactive wastes, process for solidifying radioactive wastes and solidified product |
| US5732363A (en) * | 1994-10-27 | 1998-03-24 | Jgc Corporation | Solidifying material for radioactive wastes, process for solidifying radioactive wastes and solidified product |
| RU2122754C1 (en) * | 1997-10-21 | 1998-11-27 | Производственное объединение "МАЯК" | Composition based on natural and artificial aluminosilicate materials for hardening liquid low- and medium-activity wastes with high concentration of sodium salts, among which is radioactive cesium |
| FR2844913A1 (en) * | 2002-09-20 | 2004-03-26 | Univ Pasteur | PROCESS FOR CONTAINING CESIUM AND / OR RUBIDIUM IN SINTERED CERAMIC MATRICES BASED ON EXPANDED PERLITE, MATRICES USED AND PRODUCTS THUS OBTAINED. |
| WO2004027783A3 (en) * | 2002-09-20 | 2004-05-13 | Univ Louis Pasteur Etablisseme | Method of confining caesium and/or rubidium in sintered ceramic matrices based on expanded perlite, matrices used and products thus obtained |
| RU2375773C1 (en) * | 2008-03-03 | 2009-12-10 | Федеральное государственное унитарное предприятие "Производственное объединение "Маяк" | Composition for cementing liquid radioactive wastes |
Also Published As
| Publication number | Publication date |
|---|---|
| ZA811602B (en) | 1982-03-31 |
| JPS56151399A (en) | 1981-11-24 |
| FR2479541B3 (en) | 1983-06-10 |
| FR2479541A1 (en) | 1981-10-02 |
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