CA1230221A - Method for disposal of radioactive waste involving volume reduction - Google Patents
Method for disposal of radioactive waste involving volume reductionInfo
- Publication number
- CA1230221A CA1230221A CA000457495A CA457495A CA1230221A CA 1230221 A CA1230221 A CA 1230221A CA 000457495 A CA000457495 A CA 000457495A CA 457495 A CA457495 A CA 457495A CA 1230221 A CA1230221 A CA 1230221A
- Authority
- CA
- Canada
- Prior art keywords
- waste
- radioactive
- product
- disposal
- glass
- Prior art date
- Legal status (The legal status is an assumption and is not a legal conclusion. Google has not performed a legal analysis and makes no representation as to the accuracy of the status listed.)
- Expired
Links
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
- G21F9/30—Processing
- G21F9/301—Processing by fixation in stable solid media
- G21F9/302—Processing by fixation in stable solid media in an inorganic matrix
- G21F9/305—Glass or glass like matrix
-
- 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
- G21F9/308—Processing by melting the waste
Abstract
ABSTRACT
A METHOD FOR DISPOSAL OF RADIOACTIVE WASTE
INVOLVING VOLUME REDUCTION
In a method of disposal of radioactive waste involving volume reduction, a product containing radioactive material obtained as a result of the treatment, such as by drying, calcination and/or incineration, of radioactive waste liquid and/or combustible solid, is mixed in an appropriate proportion with waste product comprising glass fibers having radioactive material adherent thereto, both wastes being generated from an atomic energy installation, and the mixture is melted by heating to be converted, on subsequent cooling, into an integrated stable solidified mass.
A METHOD FOR DISPOSAL OF RADIOACTIVE WASTE
INVOLVING VOLUME REDUCTION
In a method of disposal of radioactive waste involving volume reduction, a product containing radioactive material obtained as a result of the treatment, such as by drying, calcination and/or incineration, of radioactive waste liquid and/or combustible solid, is mixed in an appropriate proportion with waste product comprising glass fibers having radioactive material adherent thereto, both wastes being generated from an atomic energy installation, and the mixture is melted by heating to be converted, on subsequent cooling, into an integrated stable solidified mass.
Description
3~2~
A METHOD FOX DISPOSAL OF RADIOACTIVE WASTE INVOLVING
VOLUME REDUCTION
This invention is concerned with a method, involving volume reduction, for disposal of radioactive waste such as is generated from a radioactive material handling install-lion, for example a nuclear power station.
In addition to radioactive exhaust gas, atomic energy installations, such as nuclear power stations, are known to generate radioactive waste liquid, combustible solid wastes (combustible miscellaneous solids such as clothes, paper and wood, active carbon or similar materials used in air-conditi-owning systems, used ion exchange resin and waste oil, and noncombustible solid wastes (for example, glass wool and metallic parts).
Medium-level or low-level radioactive wastes, after they have been subjected to volume-reduction such as by concentra-lion, drying, calcination, incineration or compression and further subjected to various solidification treatments such as asphalt solidification and cement solidification according to their usable physical and chemical properties, are conventionally stored in the form of solidified masses.
For instance, in the case of radioactive waste liquid, reduction is achieved by converting it into a sparingly soluble material by chemical reaction and then it is separated by drying or concentration, volatile components ox being treated by calcination. The precise treatment of such liquids, as is well known, depends upon the precise nature of the liquids themselves. For example in a PER power station the liquid is mostly liquid containing boric acid used for neutron suppression and in a BAR power station it is mostly whole liquid containing sodium sulfite. Combustible solid wastes such as wood and paper are generally reduced in volume by incineration to yield ash including as principle components silicon oxide and metal oxides. Non-combustible solid wastes are often reduced in volume by compression.
The choice of such treatment is made individually, depending upon the kind of waste. In all cases improvements in efficiency of volume-reduction and stability of the solidified masses are desirable.
However, the stable solidification of the products obtained from the volume reduction treatments mentioned above often requires the addition of various additives upon solidification which increases the volume. Furthermore waste, used glass-fibers from air filters of air-conditioning systems are non-combustible and the efficiency of their volume-reduction is insufficient using the compression treatments of the prior art. As a result the amount of waste to be stored increases year by year and requires early countermeasures.
As to high-level radioactive wastes, while volume-reduction and disposal by solidifying them with glass has been tried, glass fruit of good quality is needed as a raw ~LZ30~
material for the solidifying glass. Furthermore, it is necessary to select, as glass Fritz material which has been mixed in an optimum proportion depending on the nature of the high-level radioactive waste involved. There is also a problem in that, since glass fruit of good quality is convent tonally brought for use from outside the atomic energy installation, it is expensive. The use of this fruit also obviously increases the volume of the waste.
We have now found that a product obtained as a result of drying, calcination and/or incineration, of waste liquid and combustible solid found in radioactive wastes (hereinafter sometimes called "product of incineration or the like") together with waste glass fibers contaminated by reeducate-ivity when mixed together in an appropriate proportion, Andy then combined bymelting together in a furnace, can form a stable solidified body for storage thus overcoming disadvant-ages as outlined above.
Accordingly there is provided a method of disposal of radioactive atomic energy installation waste products chafe-cterised in that a product containing radioactive material and obtained as a result of the treatment, such as by drying, calcination and/or incineration, of radio-active waste liquid and/or combustible solid, is mixed in an appropriate proportion with waste product comprising glass fibers having radioactive material adherent thereto, and the -mixture is melted by heating to be converted, on subsequent cooling, into an integrated stable solidified mass.
I
The invention will now be described in more detail with reference to the accompanying Figure 1, which is a schematic flow diagram of one preferred embodiment of the method of the invention.
In Fig. 1, a melting furnace 1 is connected with a container 2 for a product of incineration or the like, through a cutting device 2-1 for the product of incineration or the like, which device is provided with a setter 2-2. The furnace 1 is also convected with containers 3, 4 and 5 for different kinds of waste glass fibers each of which containers is provided with its own cutting device, 3-1, 4-1 and 5-1 respectively, for the waste glass fibers therein. A
device 6 for collecting melt discharged from the melting furnace 1 is also provided. The product of incineration or the like comprises ash-like powder, while the waste glass fibers are fiber-like solidified masses. When mixing these materials together in an appropriate proportion and throwing the mixture into the melting furnace 1, although the appear-private proportion can of course be attained by varying Thea amount of either material, we will describe the variation of proportions in terms of varying the amount of the product of incineration or the like with reference to the amount of the waste glass fibers.
It is to be noted that, since the compositions of waste glass fibers differ depending upon the kinds of different products used, a more stable solidified mass can be obtained by treating at the same time waste glass fibers having the ~30Z2~
same composition, which is why as shown in Fig. l the glass fibers are illustrated as being classified in-to three kinds.
However, classification into any arbitrary number of kinds is desirable depending on the different compositions of glass fibers present.
We show below, in Table 1, as one example of components of a general product of incineration or the like, the compositions, in weight %, of a calcined product of a pressurized water reactor (PER) and an incinerated product of lo a combustible miscellaneous solid body, respectively.
Table-l I Nemo tat Oxides A Praldint ted PER ¦ 20 .3 57 .3 4 ,6 17 .8 _ __ incinerated Pro- .
I duct of Combusti- 60 - 7 _ _ 40 - 30 bye Miscellaneous Solid Body . . __ It will be noted that if a radioactive waste liquid is calcined for the purpose of volume reduction, it is converted into a composition principally comprising various metal oxides containing non-volatile radioactive materials. For instance, in the case of a PER power station, boric acid B is a principal component, and in the case of a BAR power station, No is a principal component.
As regards glass wool compositions, one example of a sly representative composition of E-glass is shown in Table-2.
Components ¦ Sue ¦ ~23 ¦ A 23 ¦ Coo ¦ Others ¦
% (weight) 53-5 ¦ 3 ¦ 1~.5 18,5 For simplicity we will explain the Invention in terms of the representative container 3 for waste glass fibers in Figure l. First, a certain amount of waste glass fixers is thrown into the melting furnace l by the waste glass fiber cutting device 3-1. Next, a product of incineration or the lo like in an optimum amount for the composition of the glass fibers in the waste glass fiber container 3 and the amount thereof fed to tune furnace l is mixed into the waste glass fibers by manipulating the cutting setter 2-2.
The both materials, mixed together within the melting furnace 1, are heated to a temperature at which the waste glass fibers melt. In this case, among the various components adhering to or contained in the both materials, metals and metal oxides having higher melting points than that of the waste glass fibers may be present in the form of granular or other particulate solid material in the melt, but combustible materials are burnt, and thereby a glass-like product having a maximum overall rate of volume reduction can be produced. Furthermore, if heating is continued to a temperature at which the metals and metal oxides having higher melting points than that of the glass fibers also AVOW
melt, then the glass fibers and these metals and metal oxides melt together and become coupled in molecular struck lures to give a more stable glass-like product.
When the melting has been finished, the melt is transfer rued from the melting furnace 1 to the melt collecting container 6, then it is cooled to yield a solidified mass in which radioactivity, metals, metal oxides and the like are sealed. Alternatively the melt can be cooled and solid-fled within the melting furnace 1 without being transferred to the melt collecting container 6, and the material for disposal can be taken out of the furnace 1 in the form of a solidified mass.
The invention will now be described for the purposes of illustration only, in the following Examples of some preferred embodiments.
Example 1 Using the above-described method, a preferred mixing proportion between the waste glass wool and the product of incineration or the like is, for example, 20% of A in Table-l and 80~ White %) of glass wool. These, are mixed together and heated to about l,400C to become molten and yield a product of the following composition:
Sue Byway Aye 2 3 Coo Other Components I 46.9 18.7 11.6 0.9 14.8 7.1 I
This product on cooling is a solidified mass of the conventional borosilicate glass, and at room temperature it has strength, stability, durability and exudation- resist-ante (as represented by the weigh-t of component exuding through a unit area when forced stirring has been effected in distilled hot water at 100C).
Example 2 Using another preferred mixing proportion, 20~ of A, 25% of B and 55~ (wit I) of glass wool are mixed together and heated at l,500 - 1,600C to become molten. The compost-lion of the obtained product was as follows:
Sue Byway Allah Coo NATO Other Components 49.8 16.4 8.0 10.2 0.9 17.7 When this product was compared with the product of Example l product, they were nearly similar and no distinct differ-once was found there between in their properties.
Example 4 In another preferred disposal technique of the invent lion, the product of incineration or the like as detailed in Table l and waste glass fibers of the composition given in Table 2 were used under the conditions indicated in Table 3 below, which also details results obtained.
~313;~Z~
Table 3 Em Mixing Fusing Properties body- Prop- Temper- Pressure Time (H) of Stable mints lion azure Solidified Body Obtained _ _ ... .
Melting Inorganic cry-. for stalling mass A 2Okg about whose properties 1.5H are almost pa glass 1,400C Atoms- The them- similar to con-fibers 5 phonic portray ventional boron 1,500C Pressure is held silicate glass, 8Okg . for about in which most 1 H. metals are molten, and which has strength, stability, . durability and . exudation-res-instance.
_ _ . ............ .. __ .
Melting Properties and A 20kg for the like are about similar to pa B 25kg 1,500C Atoms- 1.5H except that the glass phonic The them- mass is colored 4b fibers ~,600C Pressure portray brown or the 55kg is held like due to for about impurities (Fe lo. or the like.
No material difference from Embodiment . pa was found.
Although the effects and advantages of the invention are apparent from the foregoing description alone, the invention can overcome difficulties which arise in connection 3~271 with the product of incineration or the like which is a pulverized material which is liable to sputter, it hugger-scopic, and needs countermeasures to be taken for maintenance and storage, and arising from the relative inefficiency of the known volume reduction by compression of the waste glass fibers. The invention further makes it possible to provide a stable solidified mass which has an extremely small exudation rate of radioactive material and which has appropriate strength and aging properties. Moreover, in the invention, lo which uses glass fibers which have become radioactive solid wastes from their presence in air filters, and which are therefore necessarily produced in atomic energy install lotions, the raw material cost is zero and increase in the amount of waste is avoided.
It will be appreciated that the appropriate proportions of the various waste products in the practice of the present invention will vary depending upon the particular install lotion and the precise nature of the washes therefrom.
However the determination of the proportions of Boyle, Sue, other metal oxides, sodium sulfite, glass etc. which should be used can be made by simple trial and error experimentation to ensure that the resultant molten and resolidified glass, that is borosilicate glass, has the required enclosing capability as well as mechanical strength.
Since glass is a noncrystalline (amorphous) material, it has a flexibility in that it can enclose foreign materials such as metal oxides and achieve the required mechanical strength in a range of appropriate amounts rather than in ~;230;;~
amounts of fixed proportions.
Since the kinds and amounts of the wastes discharged from an atomic power installation are nearly determined for each installation, a first melting experiment may be carried out in a small crucible as above described and in practice the respective amounts of the wastes described above are suitably determined at such proportions that the entire amounts of such waste glass and treated liquids and solids can be molten together without leaving any excess nor running lo into shortage, Thetis, a-t such proportions that the amounts of the waste materials which are in short supply and hence may have to be brought in from outside of the atomic power installation can be minimized, preferably can be made zero.
Such a trial~and-error experiment will determine the appropr-tale proportions for each instance.
As a matter of routine, it is of course necessary to test the molten and solidified mass obtained after the disposal to examine whether or not the disposal technique has been successful in that the radioactive waste material has been successfully enclosed in a mass of appropriate strength for storing.
A METHOD FOX DISPOSAL OF RADIOACTIVE WASTE INVOLVING
VOLUME REDUCTION
This invention is concerned with a method, involving volume reduction, for disposal of radioactive waste such as is generated from a radioactive material handling install-lion, for example a nuclear power station.
In addition to radioactive exhaust gas, atomic energy installations, such as nuclear power stations, are known to generate radioactive waste liquid, combustible solid wastes (combustible miscellaneous solids such as clothes, paper and wood, active carbon or similar materials used in air-conditi-owning systems, used ion exchange resin and waste oil, and noncombustible solid wastes (for example, glass wool and metallic parts).
Medium-level or low-level radioactive wastes, after they have been subjected to volume-reduction such as by concentra-lion, drying, calcination, incineration or compression and further subjected to various solidification treatments such as asphalt solidification and cement solidification according to their usable physical and chemical properties, are conventionally stored in the form of solidified masses.
For instance, in the case of radioactive waste liquid, reduction is achieved by converting it into a sparingly soluble material by chemical reaction and then it is separated by drying or concentration, volatile components ox being treated by calcination. The precise treatment of such liquids, as is well known, depends upon the precise nature of the liquids themselves. For example in a PER power station the liquid is mostly liquid containing boric acid used for neutron suppression and in a BAR power station it is mostly whole liquid containing sodium sulfite. Combustible solid wastes such as wood and paper are generally reduced in volume by incineration to yield ash including as principle components silicon oxide and metal oxides. Non-combustible solid wastes are often reduced in volume by compression.
The choice of such treatment is made individually, depending upon the kind of waste. In all cases improvements in efficiency of volume-reduction and stability of the solidified masses are desirable.
However, the stable solidification of the products obtained from the volume reduction treatments mentioned above often requires the addition of various additives upon solidification which increases the volume. Furthermore waste, used glass-fibers from air filters of air-conditioning systems are non-combustible and the efficiency of their volume-reduction is insufficient using the compression treatments of the prior art. As a result the amount of waste to be stored increases year by year and requires early countermeasures.
As to high-level radioactive wastes, while volume-reduction and disposal by solidifying them with glass has been tried, glass fruit of good quality is needed as a raw ~LZ30~
material for the solidifying glass. Furthermore, it is necessary to select, as glass Fritz material which has been mixed in an optimum proportion depending on the nature of the high-level radioactive waste involved. There is also a problem in that, since glass fruit of good quality is convent tonally brought for use from outside the atomic energy installation, it is expensive. The use of this fruit also obviously increases the volume of the waste.
We have now found that a product obtained as a result of drying, calcination and/or incineration, of waste liquid and combustible solid found in radioactive wastes (hereinafter sometimes called "product of incineration or the like") together with waste glass fibers contaminated by reeducate-ivity when mixed together in an appropriate proportion, Andy then combined bymelting together in a furnace, can form a stable solidified body for storage thus overcoming disadvant-ages as outlined above.
Accordingly there is provided a method of disposal of radioactive atomic energy installation waste products chafe-cterised in that a product containing radioactive material and obtained as a result of the treatment, such as by drying, calcination and/or incineration, of radio-active waste liquid and/or combustible solid, is mixed in an appropriate proportion with waste product comprising glass fibers having radioactive material adherent thereto, and the -mixture is melted by heating to be converted, on subsequent cooling, into an integrated stable solidified mass.
I
The invention will now be described in more detail with reference to the accompanying Figure 1, which is a schematic flow diagram of one preferred embodiment of the method of the invention.
In Fig. 1, a melting furnace 1 is connected with a container 2 for a product of incineration or the like, through a cutting device 2-1 for the product of incineration or the like, which device is provided with a setter 2-2. The furnace 1 is also convected with containers 3, 4 and 5 for different kinds of waste glass fibers each of which containers is provided with its own cutting device, 3-1, 4-1 and 5-1 respectively, for the waste glass fibers therein. A
device 6 for collecting melt discharged from the melting furnace 1 is also provided. The product of incineration or the like comprises ash-like powder, while the waste glass fibers are fiber-like solidified masses. When mixing these materials together in an appropriate proportion and throwing the mixture into the melting furnace 1, although the appear-private proportion can of course be attained by varying Thea amount of either material, we will describe the variation of proportions in terms of varying the amount of the product of incineration or the like with reference to the amount of the waste glass fibers.
It is to be noted that, since the compositions of waste glass fibers differ depending upon the kinds of different products used, a more stable solidified mass can be obtained by treating at the same time waste glass fibers having the ~30Z2~
same composition, which is why as shown in Fig. l the glass fibers are illustrated as being classified in-to three kinds.
However, classification into any arbitrary number of kinds is desirable depending on the different compositions of glass fibers present.
We show below, in Table 1, as one example of components of a general product of incineration or the like, the compositions, in weight %, of a calcined product of a pressurized water reactor (PER) and an incinerated product of lo a combustible miscellaneous solid body, respectively.
Table-l I Nemo tat Oxides A Praldint ted PER ¦ 20 .3 57 .3 4 ,6 17 .8 _ __ incinerated Pro- .
I duct of Combusti- 60 - 7 _ _ 40 - 30 bye Miscellaneous Solid Body . . __ It will be noted that if a radioactive waste liquid is calcined for the purpose of volume reduction, it is converted into a composition principally comprising various metal oxides containing non-volatile radioactive materials. For instance, in the case of a PER power station, boric acid B is a principal component, and in the case of a BAR power station, No is a principal component.
As regards glass wool compositions, one example of a sly representative composition of E-glass is shown in Table-2.
Components ¦ Sue ¦ ~23 ¦ A 23 ¦ Coo ¦ Others ¦
% (weight) 53-5 ¦ 3 ¦ 1~.5 18,5 For simplicity we will explain the Invention in terms of the representative container 3 for waste glass fibers in Figure l. First, a certain amount of waste glass fixers is thrown into the melting furnace l by the waste glass fiber cutting device 3-1. Next, a product of incineration or the lo like in an optimum amount for the composition of the glass fibers in the waste glass fiber container 3 and the amount thereof fed to tune furnace l is mixed into the waste glass fibers by manipulating the cutting setter 2-2.
The both materials, mixed together within the melting furnace 1, are heated to a temperature at which the waste glass fibers melt. In this case, among the various components adhering to or contained in the both materials, metals and metal oxides having higher melting points than that of the waste glass fibers may be present in the form of granular or other particulate solid material in the melt, but combustible materials are burnt, and thereby a glass-like product having a maximum overall rate of volume reduction can be produced. Furthermore, if heating is continued to a temperature at which the metals and metal oxides having higher melting points than that of the glass fibers also AVOW
melt, then the glass fibers and these metals and metal oxides melt together and become coupled in molecular struck lures to give a more stable glass-like product.
When the melting has been finished, the melt is transfer rued from the melting furnace 1 to the melt collecting container 6, then it is cooled to yield a solidified mass in which radioactivity, metals, metal oxides and the like are sealed. Alternatively the melt can be cooled and solid-fled within the melting furnace 1 without being transferred to the melt collecting container 6, and the material for disposal can be taken out of the furnace 1 in the form of a solidified mass.
The invention will now be described for the purposes of illustration only, in the following Examples of some preferred embodiments.
Example 1 Using the above-described method, a preferred mixing proportion between the waste glass wool and the product of incineration or the like is, for example, 20% of A in Table-l and 80~ White %) of glass wool. These, are mixed together and heated to about l,400C to become molten and yield a product of the following composition:
Sue Byway Aye 2 3 Coo Other Components I 46.9 18.7 11.6 0.9 14.8 7.1 I
This product on cooling is a solidified mass of the conventional borosilicate glass, and at room temperature it has strength, stability, durability and exudation- resist-ante (as represented by the weigh-t of component exuding through a unit area when forced stirring has been effected in distilled hot water at 100C).
Example 2 Using another preferred mixing proportion, 20~ of A, 25% of B and 55~ (wit I) of glass wool are mixed together and heated at l,500 - 1,600C to become molten. The compost-lion of the obtained product was as follows:
Sue Byway Allah Coo NATO Other Components 49.8 16.4 8.0 10.2 0.9 17.7 When this product was compared with the product of Example l product, they were nearly similar and no distinct differ-once was found there between in their properties.
Example 4 In another preferred disposal technique of the invent lion, the product of incineration or the like as detailed in Table l and waste glass fibers of the composition given in Table 2 were used under the conditions indicated in Table 3 below, which also details results obtained.
~313;~Z~
Table 3 Em Mixing Fusing Properties body- Prop- Temper- Pressure Time (H) of Stable mints lion azure Solidified Body Obtained _ _ ... .
Melting Inorganic cry-. for stalling mass A 2Okg about whose properties 1.5H are almost pa glass 1,400C Atoms- The them- similar to con-fibers 5 phonic portray ventional boron 1,500C Pressure is held silicate glass, 8Okg . for about in which most 1 H. metals are molten, and which has strength, stability, . durability and . exudation-res-instance.
_ _ . ............ .. __ .
Melting Properties and A 20kg for the like are about similar to pa B 25kg 1,500C Atoms- 1.5H except that the glass phonic The them- mass is colored 4b fibers ~,600C Pressure portray brown or the 55kg is held like due to for about impurities (Fe lo. or the like.
No material difference from Embodiment . pa was found.
Although the effects and advantages of the invention are apparent from the foregoing description alone, the invention can overcome difficulties which arise in connection 3~271 with the product of incineration or the like which is a pulverized material which is liable to sputter, it hugger-scopic, and needs countermeasures to be taken for maintenance and storage, and arising from the relative inefficiency of the known volume reduction by compression of the waste glass fibers. The invention further makes it possible to provide a stable solidified mass which has an extremely small exudation rate of radioactive material and which has appropriate strength and aging properties. Moreover, in the invention, lo which uses glass fibers which have become radioactive solid wastes from their presence in air filters, and which are therefore necessarily produced in atomic energy install lotions, the raw material cost is zero and increase in the amount of waste is avoided.
It will be appreciated that the appropriate proportions of the various waste products in the practice of the present invention will vary depending upon the particular install lotion and the precise nature of the washes therefrom.
However the determination of the proportions of Boyle, Sue, other metal oxides, sodium sulfite, glass etc. which should be used can be made by simple trial and error experimentation to ensure that the resultant molten and resolidified glass, that is borosilicate glass, has the required enclosing capability as well as mechanical strength.
Since glass is a noncrystalline (amorphous) material, it has a flexibility in that it can enclose foreign materials such as metal oxides and achieve the required mechanical strength in a range of appropriate amounts rather than in ~;230;;~
amounts of fixed proportions.
Since the kinds and amounts of the wastes discharged from an atomic power installation are nearly determined for each installation, a first melting experiment may be carried out in a small crucible as above described and in practice the respective amounts of the wastes described above are suitably determined at such proportions that the entire amounts of such waste glass and treated liquids and solids can be molten together without leaving any excess nor running lo into shortage, Thetis, a-t such proportions that the amounts of the waste materials which are in short supply and hence may have to be brought in from outside of the atomic power installation can be minimized, preferably can be made zero.
Such a trial~and-error experiment will determine the appropr-tale proportions for each instance.
As a matter of routine, it is of course necessary to test the molten and solidified mass obtained after the disposal to examine whether or not the disposal technique has been successful in that the radioactive waste material has been successfully enclosed in a mass of appropriate strength for storing.
Claims (2)
1. A method of disposal of radioactive atomic energy installation waste products, characterised in that a product containing radioactive material and obtained as a result of treatment by a process selected from the group consisting of drying, calcination and incineration, of radioactive waste liquid and/or combustible solid, is mixed in an appropriate proportion with waste product comprising glass fibers having radio-active material adherent thereto, and the mixture is melted by heating to be converted, on subsequent cooling, into an integrated stable solidified mass.
2. A method as claimed in claim 1, wherein the glass fiber waste products from the installation are classified into products of substantially the same composition for separate treatment of each classified product.
Applications Claiming Priority (2)
| Application Number | Priority Date | Filing Date | Title |
|---|---|---|---|
| JP22909183A JPS60122397A (en) | 1983-12-06 | 1983-12-06 | Volume decreasing treating method of radioactive waste |
| JP58-229091 | 1983-12-06 |
Publications (1)
| Publication Number | Publication Date |
|---|---|
| CA1230221A true CA1230221A (en) | 1987-12-15 |
Family
ID=16886606
Family Applications (1)
| Application Number | Title | Priority Date | Filing Date |
|---|---|---|---|
| CA000457495A Expired CA1230221A (en) | 1983-12-06 | 1984-06-26 | Method for disposal of radioactive waste involving volume reduction |
Country Status (3)
| Country | Link |
|---|---|
| EP (1) | EP0155418A3 (en) |
| JP (1) | JPS60122397A (en) |
| CA (1) | CA1230221A (en) |
Cited By (1)
| Publication number | Priority date | Publication date | Assignee | Title |
|---|---|---|---|---|
| US9029278B2 (en) | 2008-12-30 | 2015-05-12 | Areva Nc | Alumino-borosilicate glass for the confinement of radioactive liquid effluents, and method for treating radioactive liquid effluents |
Families Citing this family (6)
| Publication number | Priority date | Publication date | Assignee | Title |
|---|---|---|---|---|
| JPS62222198A (en) * | 1986-03-25 | 1987-09-30 | 動力炉・核燃料開発事業団 | Manufacture of cartridge for processing radioactive waste liquor |
| DE4118123A1 (en) * | 1991-06-03 | 1992-12-10 | Siemens Ag | METHOD AND DEVICE FOR TREATING A RADIOACTIVE WASTE SOLUTION |
| JPH05249294A (en) * | 1992-03-03 | 1993-09-28 | Nuclear Fuel Ind Ltd | Method of solidifying and disposing of radioactive contaminant |
| FR3009642B1 (en) * | 2013-08-08 | 2018-11-09 | Areva Nc | PROCESS AND INSTALLATION FOR INCINERATION, FUSION AND VITRIFICATION OF ORGANIC AND METAL WASTE |
| CN113990544A (en) * | 2021-10-28 | 2022-01-28 | 武汉理工大学 | Method for curing medium-low-level glass fiber and high-level waste liquid in cooperation with glass |
| KR102615509B1 (en) * | 2023-04-05 | 2023-12-19 | (주)한국원자력 엔지니어링 | Radioactive waste solidification and immobilization method |
Family Cites Families (3)
| Publication number | Priority date | Publication date | Assignee | Title |
|---|---|---|---|---|
| DE2731327C3 (en) * | 1977-07-12 | 1981-01-22 | Kernforschungszentrum Karlsruhe Gmbh, 7500 Karlsruhe | Process for filtering dust from radioactive waste gases and equipment for carrying out the process |
| DE3110192A1 (en) * | 1981-03-17 | 1982-10-07 | Kernforschungszentrum Karlsruhe Gmbh, 7500 Karlsruhe | METHOD FOR COATING RADIOACTIVELY CONTAMINATED OR RADIOACTIVE SOLIDS CONTAINING SOLUTIONS FROM NUCLEAR TECHNICAL PLANTS WITH A REPOSABLE MATRIX |
| DE3142356A1 (en) * | 1981-10-26 | 1983-05-11 | Alkem Gmbh, 6450 Hanau | "METHOD FOR FINAL CONDITIONING RADIOACTIVE AND / OR TOXIC WASTE" |
-
1983
- 1983-12-06 JP JP22909183A patent/JPS60122397A/en active Pending
-
1984
- 1984-06-04 EP EP84303715A patent/EP0155418A3/en not_active Withdrawn
- 1984-06-26 CA CA000457495A patent/CA1230221A/en not_active Expired
Cited By (1)
| Publication number | Priority date | Publication date | Assignee | Title |
|---|---|---|---|---|
| US9029278B2 (en) | 2008-12-30 | 2015-05-12 | Areva Nc | Alumino-borosilicate glass for the confinement of radioactive liquid effluents, and method for treating radioactive liquid effluents |
Also Published As
| Publication number | Publication date |
|---|---|
| EP0155418A2 (en) | 1985-09-25 |
| JPS60122397A (en) | 1985-06-29 |
| EP0155418A3 (en) | 1986-11-20 |
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