AU643943B2 - Processing of a dry precursor material - Google Patents

Processing of a dry precursor material Download PDF

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AU643943B2
AU643943B2 AU46317/89A AU4631789A AU643943B2 AU 643943 B2 AU643943 B2 AU 643943B2 AU 46317/89 A AU46317/89 A AU 46317/89A AU 4631789 A AU4631789 A AU 4631789A AU 643943 B2 AU643943 B2 AU 643943B2
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Australia
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container
gas
outlet
inlet
precursor material
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AU4631789A (en
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Eric John Ramm
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Australian Nuclear Science and Technology Organization
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Australian Nuclear Science and Technology Organization
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Description

VRErION PCr ep j B WORLD INTELLECTUAL PROPERTY ORGANIZATION International Bureau INTERNATIONAL APPLICATION PUBLISHED UNDER THE PATENT COOPERATION TREATY (PCT) (51) International Patent Classification 4 (I1) International Publication Number: WO 90/05984 G21F 9/30, 9/32, 9/36 Al (43) International Publication Date: 31 May 1990 (31.05.90) 2 1l Internation A Application Number: PCT/AU89/00500 (81) Designated States: AT, AT (European patent), AU, BB, BE (European patent), BF (OAPI patent), BG, BJ (OAPI (22) International Filing Date: 17 November 1989 (17.11.89) patent), BR, CF (OAPI patent), CG (OAPI patent), CH, CH (European patent), CM (OAPI patent), DE, DE (European patent), DK, ES, ES (European patent), FI, Priority data: FR (European patent), GA (OAPI patent), GB, GB (Eu- PJ 1556 !8 November 1988 (18.11.88) AU rapean patent), HU, IT (European patent), JP, KP, KR, LU, LU (European patent), MC, MG, ML (OAPI patent), MR (OAPI patent), MW, NL, NL (European (71) Applicant (for all designated States except US): AUSTRAL- patent), NO, -RO, SD, SE, SE (European patent), SN IAN NUCLEAR SCIENCE TECHNOLOGY OR- (OAPI patent), SU, TD (OAPI patent), TG (OAPI pa- GANISATION [AU/AU]; New Illawarra Road, Lucas tent), US.
Heights, NSW 2234 (AU).
(72) Inventor; and Published Inventor/Applicant (for US only) RAMM, Eric, John [AU/ With international sear-'i report.
AU]; 10 Immarna Street, Lilli Pilli, NSW 2229 (AU).
(74) Agent: GRIFFITH HACK CO.; 71 York Street, 2nd Floor, G.P.O. Box 4164, Sydney, NSW 2000 6 (54) Tle: PROCESSING OF A DRY PRECURSOR MATERIAL (57) Abstract 27 2 A container (13) is arranged to be filled with a dry precursor material 21 26 and the top of the container is welded shut. The container has a generally cylindrical shape with at least a partially corrugated side wall The top L' of the container (27) has a filling port (21) and a plug (22) adapted to fit 13 therein. A cylindrical liner (24) fits snugly within the container (13) and ex- 29 tends between an inlet and outlet filter (25) and (26) which are located at the bottom (20) and top (27) of the container respectively. At the centre of the top of the container a gas outlet is provided the gas outlet (28) is 32 in the form of a vertical extending pipe which passes through the plug (22) and terminates in a transverse perforated pipe (29) at its lower end. The perforated pipe (29) is separated from the dry percursor material within the container by the outlet filter At the bottom of the container, a gas inlet is provided in one side wall of the container, inside the container the 23 pipe (30) extends horizontally parallel to the bottom of the container. It is also perforated and is separated from the dry precursor material by the inlet filter The container is heated in either a batch or continuous process 33 while a reducing gas such as hydrogen or nitrogen is introduced at the gas inlet This gas passes from the perforated pipe (31) and eventually 24i passes through outlet pipe The container is heated for a time sufficient to ensure that substantially all the nitrates within the dry precursor material have beer, decomposed and removed.
34 31 2 S(Referred to in PCT Gazette No. 16/1990. Section II).
WO 90/05984 PCT/AU89/00500 -1- PROCESSING OF A DRY PRECURSOR MATERIAL TECHNICAL FIELD The present invention relates to a method of processing a dry precursor material incorporating radioactive waste.
The invention is particularly concerned with the incorporation of high level radioactive waste within an immobilising substance such as synthetic rock or glass.
BACKGROUND OF THE INVENTION An existing arrangement for producing synthetic rock precursor incorporating high level radioactive waste involves the production of synthetic rock precursor using tetraisopropyltitanate and tetrabutylzirconate as ultimate sources of titanium oxiLd TiO 2 and ZrO 2 The components are mixed with nitrate solutions of other components, coprecipitated by addition of sodium hydroxide and then washed. The precursor thus produced is mixed in a hot cell with high level nuclear waste in the form of a nitrate solution to form a thick homogenous slurry. The slurry is then fed to a rotary kiln in which the slurry is heated, devolatilized and calcined to produce a powder which is then mixed with metallic titanium powder and poured into containers for hot pressing.
The containers which are used for this purpose have a generally cylindrical wall of bellows-like formation. Heat and pressure is applied to each container and its contents, and a synthetic rock product is formed within the container with the high level radioactive waste suitably immobilised therein.
A system for producing synthetic rock as described above has a number of deficiencies which will now be outlined.
WO 90/05984 PCT/AU89/00500 -2- The apparatus required to produce the synthetic rock requires that a slurry incorporating high level radioactive waste be fed into a calciner. The calciner must be free of oxygen by the use of a reducing gas and at the same time the slurry must be heated and dried.
A calciner which meets all these objectives is a large and cumbersome apparatus with numerous working parts on which it is difficult to perform maintenance on. Typically, a rabble bar is required within the calciner to prevent caking of the slurry and a filtration system is required to prevent escape of radioactive dust.
The present invention provides an alternative method for use in forming a substance incorporating immobilised radioactive waste.
DISCLOSURE OF THE INVENTION According to the present invention, there is provided a method of processing a dry precursor material incorporating radioactive waste comprising: filling a container with dry precursor material incorporating radioactive waste and nitrate components, the container having a generally cylindrical shape with at least a partially corrugated side wall, a gas outlet, an outlet filter, a gas inlet and an inlet filter; sealing the container excepting the gas inlet and outlet; heating the container and its contents while feeding a gas through the gas inlet, inlet filter and dry precursor material; and collecting exhaust gas passing through the outlet filter and gas outlet; whereby a dry calcined material incorporating radioactive waste is produced in a form in which substantially all nitrate components have been decomposed and removed.
Preferably deleterious effects of the dried calcined material when in the form of a synthetic rock precursor are avoided by providing that the gas is a reducing gas such as
H
2 WO 90/05984 PCT/AU89/00500 -3- Preferably, the method includes a step of hot isostatically or uniaxially pressing the container once substantially all the nitrate components 1 ave been decomposed and removed.
The gas inlet and outlet are preferably arranged at opposite ends of the container.
Alternatively, the gas inlet and outlet may be located on the side wall of the container or atthe same end.
The gas inlet and outlet may both be connected with a perforated inlet and outlet pipe respectively which are located within the container and are separated from the dry precursor material by the inlet and outlet filters respectively.
Preferably, the container has a dumb-bell shape.
The container is preferably provided with a filling port which is arranged to permit filling of the container with dry precursor material.
It is preferred that a step be provided for inserting a plug in the filling port after the container has been filled with dry precursor material.
Preferably, the plug incorporates the gas outlet.
The plug may be welded in position to provide a seal which prevents escape of material from within the container.
Preferably, the inlet and outlet filters are disc-like in shape and are located at the base and top of the cor.tainer respectively.
Preferably, the gas filters have a diameter substantially the same as the maximum diameter ou the container.
4 It it preferred that the container be provided with a cylindiicel liner to prevent dry precursor material from locating itself within the corrugations of the container.
The container may also be provided with a heat transfer and stabilising plate.
The inlet and outlet filter preferably comprise a perforated shroud.
The inlet and outlet filter may be formed from a ceramic fibre such as zirconium oxide which is substantially only pervious to gas.
According to one embodiment of the present invention, the gas which is introduced through the gas inlet is a reducing gas such as hydrogen or nitrogen with three percent by volume hydrogen.
A back pressure may be provided at the gas outlet to reduce prob2-'ms associated with channelling in the container.
Preferably, the exhaust gas is fed through a water reservoir which provides the back pressure.
The present invention also provides a method of producing a dry calcined material incorporating radioactive waste, comprising: mixing radioactive waste with a particulate material and applying heat thereto to form a dry precursor material impregnated with radioactive waste and incorporating nitrate components; feeding the dry precursor material into a container having a generally cylindrical shape with at least a partially corrugated side wall, a gas outlet, an outlet filter, a gas inlet and inlet filter; sealing the container excepting the gas inlet and outlet; 1
I
1 0 :1316CIW heating the container and its contents while feeding gas through the gas inlet, inlet filter and dry precursor material, collecting exhaust gas passing through the outlet filter and gas outlet; and producing a dry calcined material incorporating radioactive waste in which substantially all nitrate components have been decomposed and removed.
Preferably, the dry precursor material is mixed and heated in a heating chamber having a screw discharge means.
A volumetric feeder may be used to fet- the particulate material into the heating chamber.
The radioactive waste may be sprayed onto the particulate material in the heating chamber. Preferably, the dry precursor material is mixed in the heating chamber by a mixer rotatable about a horizontal axis.
The heating chamber may be connected with a discharge hopper comprising a vertical screw conveyor for feeding the dry precursor material into a container.
In one embodiment, after the heating step, the gas inlet of each container is crimped and the container is evacuated through the outlet which is then crimped to provide a gas tight container. This container can then be further processed to form a final material which, when cold, safely immobilises the radioactive waste.
Furthermore, since the cold material has a smaller volume "due to reactions in the further processing, with advantage the container can be compressed.
The dry precursor material can be converted to a stable inorganic solid such as glass, glass ceramic, ceramic, or synthetic rock.
1 31601W 6 Furthermore, the invention also consists in a method of processing dry precursor material incorpcrating radioactive waste comprising: filling a container with glass forming powder incorporating radioactive waste and nitrate components, the container having a generally cylindrical shape with at least a partially corrugated side wall, a gas outlet, an outlet filter, a gas inlet and an inlet filter; sealing the container excepting the gas inlet and outlet; heating the container and its contents while feeding a gas through the gas inlet, inlet filter and dry precursor material; collecting exhaust gas passing through the outlet filter and gas outlet; further processing at elevated temperature to form a molten glass and allowing the containers to cool whereby a glass is produced in a form in which substantially all nitrate components have been decomposed and removed.
Embodiments of the invention may offer the advantage of substantially reducing loss of volatile radioactive components and reducing the loss of dust compared with alternative methods. Furthermore, embodiments of the present invention eliminate the neee apparatus such as a rotary calciner and therefore avoids problems associated with moving parts and wet and dry seals required in such equipment.
S 25 DESCRIPTION OF THE DRAWINGS Embodiments of the present invention will now be described by way of example only with reference to the accompanying drawings in which: Figure 1 shows a method of producing a synthetic rock precursor material impregnated with radioactive waste; Figure 2 shows a bellows container for the process shown in Figure 1; Figure 3 shows a dumbbell container for the process shown in Figure 1; and :1 3160 1W S •t 6a Figure 4 shows a method of producing glass impregnated with radioactive waste.
BEST MODE OF CARRYING OUT THE INVENTION A method of producing a synthetic rock precursor material irrpregnated with radioactive waste will now be described with reference to Figure 1.
Particulate material in the form of a dry granulated powder in a hopper 1 is fed to a heating chamber 4 by means of a volumetric feeder 5. High level radioactive waste is fed by means of a conduit 2 through a metering pump 3 and is sprayed onto the particulate material within the heating chamber 4 by means of perforated tubing 6.
S
S:131601W WO 90/05984 PCT/AU89/00500 -7- High level radioactive waste is mixed with the particulate material in the heating chamber 4 and gases which evolve during heating are removed therefrom by means of an off gas pipe 8.
The particulate material incorporating high level radioactive waste is removed from the heating chamber 4 by means of a screw discharge conveyor 9. At this stage, it is in the form of a dry precursor material.
The screw discharge conveyor feeds the dry precursor material into a conduit where it falls under the action of gravity into a hopper 11. A vertical screw discharge conveyor located in the hopper 11 is used to transfer the dry calcined material into respective containers at the bottom of the hopper 11.
2ach container 13 is supported on a vertically movable table which enables a container which has been filled with dry precursor material to be lowered so that a lid can be welded on top of it to provide an air tight seal excepting for a gas inlet and outlet.
Once each container has been filled and welded shut, it may be processed in either a batch 15 or as part of a continuous feeding system 16 in a manner which will be described later.
Each container once it has be, processed is then evacuated by first crimping the inlet and then using a suction device to remove any gas. The container is then completely sealed by crimping the outlet and is then transferred to a furnace 17 for hot isostatic or uniaxial pressing whereby the dry precursor material is transformed into a synthetic rock in which the high level radioactive waste is immobilized therein. The container is then removed from the furnace 17 and is conveyed through a continuous cooling chamber 18.
WO 90/05984 PCIT/AU89/00500 -8- The containers used in the method described with reference to Figure 1 will now be described in more detail.
The containers may be as shown either in Figure 2 or Figure 3.
Effectively, the container is a cylinder in Figure 2 having a corrugated side wall 23. The top of the container 27 has a filling port 21 and a plug 22 adapted to fit therein.
A cylindrical liner 24 fits snugly within the container 13 and extends between an inlet and outlet filter 25 and 26 which are located at the bottom 20 and top 27 of the container respectively.
Both the inlet and outlet filter are effectively disc like in shape and are formed from a ceramic fibre material such as zirconium oxide or titanium oxide fibre.
At the centre of the top of the contaiier 27, a gas outlet is provided 28. The gas outlet 28 is in the form of a vertically extending pipe which passes through the plug 22 and terminates in a transverse perforated pipe 29 at its lower end. The perforated pipe 29 is separated from the dry precursor material within the container by the outlet filter 26.
At the bottom of the container, a gas inlet 30 is provided in one side wall of the container. Inside the container the pipe 30 extends horizontally, parallel to the bottom of the container. It is also perforated and is separated from the dry precursor material by the inlet filter Within the liner 24 heat transfer stabilising plates 32 and 33 are provided which divide the container into three distinct chambers. The heat transfer and stabilising plates help prevent deformation of the container during hot WO 90/05984 PCT/AU89/00500 -9uniaxial pressing of the container and in addition provide a means of assisting heat transfer within the container.
A perforated shroud 34 may also be provided as a containment structure for the inlet filter.
In Figure 3 an alternative construction of the container 13 is shown in which a dumb-bell shape 35 is utilised. Effectively, the components of this type of container are the same as that shown in Figure 2, however, the liner 24 and heat transfer and stabilising plates are not required.
With regard to the actual method of processing a dry precursor material to make as synthetic rock within a container shown in Figure 2 or Figure 3, a container is heated in either a batch or a continuous process while a reducing gas such as hydrogen or nitrogen with three percent by volume hydrogen is introduced at the gas inlet 30. This gas passes from the perforated pipe 31 through the inlet filter 35, through the dry precursor material, through the outlet filter 26 and out through the outlet pipe 29 and 28.
A back pressure is provided at the outlet pipe 28 by feeding the exhaust gas passing through the outlet pipe 28 into a reservoir filled with water. The back pressure ensures that the reducing gas is evenly distributed through the dry precursor material as it passes through the container, and this reduces channelling.
The container is heated to a temperature such as 750 C for a time sufficient to ensure that substantially all the nitrates within the dry precursor material have been decomposed and removed. Thus a calcination process is effectively carried out within the container.
The advantages of the embodiment described above are outlined as follows: WO 90/05984 PCT/AU89/00500 Firstly because the calcination process takes place within the container rather than within a large volume calciner, the costs associated with producing a synthetic rock incorporating radioactive waste are significantly reduced.
In addition because a large rotary calciner is eliminated from the process, associated difficulties iii retaining gas tight seals and maintenance of mechanical components are also significantly reduced.
Further, a titanium metal addition stage after calcination is eliminated and the loss of volatile components during calcination is also reduced.
An embodiment of the present invention will now be described with reference to Figure 4 which shows a method of using a dry precursor mpterial to produce a glass incorporating high level radioactive waste.
In essence the method shown in Figure 4 is similar to that shown in Figure 1 although there are slight modifications due to the differences in process requirements between glass and synthetic rock.
Glass forming powder is fed into a hopper 41 and by means of a volumetric feeder 45 is fed into a heating chamber 44. High level radioactive waste is fed by means of a conduit 42 from a storage container through a metering pump 43 and is sprayed onto glass forming powder within the heating chamber 44 by means of a sprinkler system 46.
Within the heating chamber, high level radioactive waste is mixed and heated with the glass forming powder. The mixing is performed by a mixer which is rotatable about a horizontal axis.
Gases which are evolved by the heating process within the heating chamber 44 are removed from the heating chamber by means of an off gas pipe (not shown).
IF
WO 90/05984 PCT/AU89/)0560 -11- The glass formina powder incorporating high ltvel radioactive waste is discharged into a hopper 48 and is then fed by means of a volumetric feeder 50 to a discharge hopper 51.
A container 52 below the hopper 51 is then filled with glass forming powder and may then be welded shut in the same manner as described in the process of Figure 1.
A comparison of the shape of the cor.tainer 52 shown in Figure 4 and that shown in Figures 1 to 3 highlights that it is not necessary to have the side wall of the container provided with corrugations from top to bottom.
The actual method of processing the glass forming powder within the container 52 is essentially the same as that used to process the synthetic rock precursor material within the containers shown in Figure 2 or 3. One major difference however is that air or inert gas may be fed into the inlet 54 (inlet 30 of figure 2) rather than a reducing gas. This is because of the different chemical properties of glass forming powder.
Another difference is that during the heating of the container 52 within the furnace 53, nitrates are decomposed and removed after heating to approximately 750 0 C. On further heating from 11000 to 1300°C, the powder mixture is vitrified. The result is that glass which forms within the container 52 occupies less volume than the glass forming powder.
WO 90/05984 PCT/AU89/00500 -12- Thus space exists at the top of the container and this space corresponds with the part of the container which has a corrugated side wall if a cr.ctainer with a partially corrugated side wall is utilised.
Once the container is removed from the furnace 53 the top of the container can be compressed by any suitable compressing means and the resultant product is glass having high level radioactive waste immobolised therein.

Claims (35)

1. A method of processing dry precursor material incorporating radioactive waste comprising: filling a container with dry precursor material incorporating radioactive waste and nitrate components, the container having a generally cylindrical shape with at least a partially corrugated side wall, a gas outlet, an outlet filter, P gas inlet and an inlet filter; sealing the container excepting the gas inlet and outlet; heating the container and its contents while feeding a gas through the gas inlet, inlet filter and dry precursor material; and collecting exhaust gas passing through the outlet filter and gas outlet; whereby a dry calcined material incorporating radioactive waste is produced in a form in which substantially all nitrate components have bean decomposed and removed.
2. A method according to claim 1, wherein deleterious effects of the dried calcined material when in the form of a synthetic rock precursor are avoided by providing that the gas is a reducing gas.
3. A method according to claim 1 or 2, wherein the method includes a step of hot isostatically or uniaxially pressino the container onca substantially all the nitrate components have been decomposed and removed.
4. A method according to claim 1, wherein the gas outlet and inlet are arranged at opposite ends of the container.
A method according to claim 1, wherein the gas inlet and outlet are located on the side wall of the container or at the same end.
6. A method according to claim 4, wherein the gas inlet and outlet are both arranged to be connected with a perforated inlet and outlet pipe respectively which are located within the container and are separated from the dry precursor material by the inlet and outlet filters respectively. WO 90/05984 PCT/AU89/00500 -14-
7. A method according to claim 6, wherein the container has a dumb-bell shape.
8. A method according to claim 1, wherein the dry precursor material is glass powder.
9. A method of processing a dry precursor material incorporating radioactive waste comprising: filling a container with dry precursor material incorporating radioactive waste and nitrate components, the container having a generally cylindrical shape with at least a partially corrugated side wall, a gas outlet, an outlet filter, a gas inlet and an inlet filter; sealing the container excepting the gas inlet and oitlet; heating the container and its contents while feeding a reducing gas through the gas i'alet, inlet filter and dry precursor material; and collecting exhaust gas passing through the outlet filter and gas outlet; whereby a dry calcined material incorporating radioactive waste is produced in a form in which deleterious effects have been substantially avoided and substantially all nitrate components have been decomposed and removed.
A method according to claim 9, including a step of hot isostatically or uniaxially pressing the container once substantially all the nitrate components have been decomposed and removed.
11. A method according to claim 10, wherein the gas inlet and outlet are arranged at opposite ends of the container.
12. A method according to claim 11, wherein the gas inlet and outlet are both connected with a perforated inlet and outlet pipe respectively which are located within the container and are separated from the dry precursor material by the inlet and outlet filters respectively.
13. A method according to claim 12, wherein the container has a dumb-bell shape. 15
14. A method according to claim 9, wherein the container is provided with a filling port which is arranged to permit filling of the container with dry precursor material and a step is provided for inserting a plug in the filling port after the container has been filled with dry synthetic rock precursor material.
A method according to claim 14, wherein the plug incorporates the gas outlet.
16. A method according to claim 15,7 wherein the gas filters are disc-like in -ape and are located at the base and top of the container respectively and have a diameter substantially the same as the maximum diameter of the container.
17. A method according to -laim 16, wherein the container is provided with a cylindrical liner to prevent dry precursor material from locating itself within the corrugations of the container.
18. A method according to claim 9, wherein the conta-ner is provided with a heat transfer and stabilising plate.
19. A method according to claim 18, wherein the inlet and outlet filter preferably comprise a perforated shroud.
20. A method according to claim 19, wherc?'- the S 25 inlet and outlet filter are formed from a ceramic fibre such as zirconium oxide which is substantially only pervious to gas.
21. A method according to claim 20, wherein the gas which is introduced through the gas inlet is nitrogen with three percent by volume hydrogen.
22. A method according to claim 9, wherein a back pressure is provided at the gas outlet to reduce problems associated with channelling in the container.
23. A method according to claim 22, wherein the S 35 exhaust gas is fed through a water reservoir which *provides the back pressure.
24. A method of producing a dry calcined material incorporating radioactive waste, comprising: :13160iW 16 mixing radioactive waste with particulate material and applying heat thereto to form a dry precursor material impregnated with radioactive waste and incorporating nitrate components; feeding the dry precursor material into a container having a generally cylindrical shape with at least a partially corrugated side wall, a c..s outlet, an outlet filter, a gas inlet and inlet filter sealing the container excepting the gas inlet and outlet; heating the container and its contents while feeding gas through the gas inlet, inlet filter and dry precursor material, collecting exhaust gas passing through the outlet filter and gas outlet; and producing a dry calcined material incorporating radioactive waste in which substantially all nitrate components have been decomposed and removed.
A method according to claim 24, wherein the dry precursor material is mixed and heated in a heating chamber having a screw discharge means.
26. A method according to claim 24 or 25, wheiein a volumetric feeder is used to feed the particulate material into the heating chamber.
S.27. A method according to anyone of claims 24 to 26, wherein the radioactive waste is sprayed onto the particulate material in the heating chamber.
28. A method according to anyone of claims 24 to 27, .o wherein the dry precursor material is mixed in the heating chamber by a mixer rotatable about a horizontal axis.
29. A method accurding to anyone of claims 24 to 28, wherein the heating chamber is connected with a discharge hopper comprising a vertical screw conveyor for feeding the dry precursor material into a container.
30. A method according to anyone claims 24 to 29, wherein the particulate material is a synthetic rock precursor and the containers containing the dry calcined material are further processed by applying high 1,S:131601W 17 temperature and pressure to form a synthetic rock matrix immobilising radioactive waste.
31. A method according to claim 30, wherein before applying high temperature and pressure each container is evacuated and closed in a gas tight manner.
32. A method of processing dry precursor material incorporating radioactive waste comprising: filling a container with glass forming powder incorporating radioactive waste and nitrate components, the container having a generally cylindrical shape with at least a partially corrugated side wall, a gas outlet, an outlet filter, a gas inlet and an inlet filter; sealing the container excepting the gas inlet and outlet; heating the container and its contents while feeding a gas through the gas inlet, inlet filter and dry precursor material; collecting exhaust gas passing through the outlet filter and gas outlet; further processing at elevated temperature to form a molten glass and allowing the containers to cool whereby a glass is produced in a form in which substantially all nitrate components have been decomposed and removed.
33. A method according to claim 32 wherein the gas is an inert gas.
34. A method as claimed in claim 32 or 33 and including before the further processing, the container is evacuated and closed in a gas tight mzviner, and after the further processing at elevated temperature, the container is compressed around the glass.
35. A method of processing precursor material and radioactive waste which includes nitrate components e substantially as herein described with reference to Fig 1 or Fig 4 of the accompanying drawings. S S:131601W
AU46317/89A 1988-11-18 1989-11-17 Processing of a dry precursor material Ceased AU643943B2 (en)

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AUPJ1556 1988-11-18
AUPJ155688 1988-11-18
AU46317/89A AU643943B2 (en) 1988-11-18 1989-11-17 Processing of a dry precursor material

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AU643943B2 true AU643943B2 (en) 1993-12-02

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Citations (3)

* Cited by examiner, † Cited by third party
Publication number Priority date Publication date Assignee Title
AU524883B2 (en) * 1980-07-15 1982-10-07 Australian Atomic Energy Commission Containing waste material
EP0115311A1 (en) * 1983-01-26 1984-08-08 Asea Ab Process for encapsulating radioactive or noxious materials, and container for carrying out this process
AU597385B2 (en) * 1986-06-25 1990-05-31 Australian National University, The Encapsulation of waste materials

Patent Citations (3)

* Cited by examiner, † Cited by third party
Publication number Priority date Publication date Assignee Title
AU524883B2 (en) * 1980-07-15 1982-10-07 Australian Atomic Energy Commission Containing waste material
EP0115311A1 (en) * 1983-01-26 1984-08-08 Asea Ab Process for encapsulating radioactive or noxious materials, and container for carrying out this process
AU597385B2 (en) * 1986-06-25 1990-05-31 Australian National University, The Encapsulation of waste materials

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