US3749917A - Device for encapsulating a radioactive resin-water slurry - Google Patents

Device for encapsulating a radioactive resin-water slurry Download PDF

Info

Publication number
US3749917A
US3749917A US00142788A US3749917DA US3749917A US 3749917 A US3749917 A US 3749917A US 00142788 A US00142788 A US 00142788A US 3749917D A US3749917D A US 3749917DA US 3749917 A US3749917 A US 3749917A
Authority
US
United States
Prior art keywords
drum
mixture
cement
resin
container
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 - Lifetime
Application number
US00142788A
Inventor
H Kucherer
Current Assignee (The listed assignees may be inaccurate. Google has not performed a legal analysis and makes no representation or warranty as to the accuracy of the list.)
Individual
Original Assignee
Individual
Priority date (The priority date 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 date listed.)
Filing date
Publication date
Application filed by Individual filed Critical Individual
Application granted granted Critical
Publication of US3749917A publication Critical patent/US3749917A/en
Anticipated expiration legal-status Critical
Expired - Lifetime legal-status Critical Current

Links

Images

Classifications

    • GPHYSICS
    • G21NUCLEAR PHYSICS; NUCLEAR ENGINEERING
    • G21FPROTECTION AGAINST X-RADIATION, GAMMA RADIATION, CORPUSCULAR RADIATION OR PARTICLE BOMBARDMENT; TREATING RADIOACTIVELY CONTAMINATED MATERIAL; DECONTAMINATION ARRANGEMENTS THEREFOR
    • G21F5/00Transportable or portable shielded containers
    • G21F5/005Containers for solid radioactive wastes, e.g. for ultimate disposal

Definitions

  • ABSTRACT A device and process wherein a metallic drum is lined with a layer of cement and vermiculite and evacuated. An injection header is fitted to and extends into the hol low interior of the lined drum to permit access of radioactive waste comprising a resin-water slurry. The hollow interior of the drum may fill with resins while the cement-vermiculite layer uniformly absorbs the water therefrom.
  • This invention relates to a device and process for the encapsulation of radioactive waste, and more particularly to prepared containers for receiving radioactive resin-water slurries.
  • the presently preferred technique for packaging radioactive waste materials comprises centrifuging the slurry to dewater the resinous material, mixing the resins with cement in a cement mixer, and allowing this mixture to harden in a drum.
  • the water from the slurry is generally poured into a prepared drum of cement mixed with vermiculite.
  • a drum is first prepared by placing a layer of cement or cement and vermiculite on its bottom.
  • a cylindrical retainer assembly is then inserted such that an annular layer and a top layer of cement or cement-vermiculite can be poured. Subsequently the conductor injection header extending into the interior of the layers is fitted to the drum and to the lid thereof.
  • the drum is then evacuated so that air does not inhibit the ingress of the slurry and such that the vacuum produced aids in the uniform dewatering of the resinwater slurry.
  • the chamber formed by the cement mixture, the water is drawn into and uniformly dispersed within the mixture.
  • the chamber therefore is substantially free of water and its entire volume may be utilized to store resinous material.
  • an encapsulation container 10 in accordance with this invention, surrounded by a shield 12 which may be of lead filled steel, as is known in this art.
  • the container 10 essentially comprises: a drum l4 sealed by a lid 16, both of which may be suitably made of carbon steel; a liner 18 of cement or of a mixture of cement and vermiculite; and an injection header or conduit 20.
  • the container 10 is preferably prepared as follows:
  • a mix is prepared which suitably consists of any of the common forms of cement; either alone, or preferably in combination with vermiculite.
  • a bottom layer 22 of mix is placed in the drum 14.
  • An inner retainer 24 which has an injection coupling 21 fitted thereto is then situated centrally within the drum l4 and is supported on the bottom layer 22.
  • the inner retainer 24 preferably includes a cylindrical side portion 26 and a top 28 and a bottom 30.
  • a plurality of openings 31 are provided in the cylindrical side portion 26 for egress of liquid.
  • the openings 31 are preferably at the bottom of the retainer 24.
  • the remaining volume of the drum l4 exterior to the retainer 24 is filled with the mix.
  • Pins 25 may be provided to aid in maintaining the position of the retainer 24.
  • the drum lid 16 may then be installed and locked to the drum 14 with a common bolted closing ring 32.
  • the lid 16 should have its center contacting and supported by a flange 33 on the injection coupling 21.
  • the shield 12 may be most conveniently utilized when comprising two sections; a drum support section 34 and a sleeve section 36 which can be releasably locked to the support section 34, as by pins 35.
  • the injection header 20 is then fitted to the container 10.
  • the injection header 20 comprises a vacuum header 38 which is open and externally threaded at its bottom, as indicated by the numeral 39, and sealed at its top to a resin-water slurry injection pipe 40, as by welding.
  • the external threads 39 are arranged to engage with threads 41 on the drum lid 16.
  • the pipe 40 extends through the injection coupling 21 into the chamber 42 formed by the liner 18.
  • a vacuum test line 44 is also fitted to the vacuum header 38.
  • the slurry injection pipe 40 has a valve 46 fitted therein, and the vacuum line 44 has a vacuum gauge 48 fitted thereto.
  • the pipe 40 extends to a resin-water slurry hold-up tank (not shown).
  • a vacuum conduit 49 which is connected to vacuum pump (not shown) and which contains a valve 50 is connected to pipe 40 above the vacuum header 38.
  • valve 46 is closed and valve 50 is opened and the vacuum pump is utilized to evacuate the drum 14 for example 7% to 9 pain for a 30 gallon drum with a 3 inch liner 18. Holes 52 are provided in the flange 33 to assure communication between the evacuated liner l8 and the vacuum header 38. Valve 50 is then closed and valve 46 opened to admit the resin-water slurry to the interior of drum l4.
  • the resin-water slurry entering through pipe 40 extending a short distance into chamber 42 is prohibited from eroding the bottom layer 22 of the liner 18 by the bottom portion 30 of the retainer 24.
  • the resins accumulate within central chamber 42.
  • the water passes through the holes 31 in the inner retainer 24 and is drawn into the liner 18.
  • the water substantially uniformly wets the entire liner 18 since the vacuum constantly causes the liquid to migrate from relatively filled" regions to unfilled regions, i.e., those still possessing a relatively low pressure due to evacuation.
  • the liner l8 subsequently hardens chemically.
  • Valve 46 is closed when the container 10 is completely full.
  • the "full state" may be ascertained by noting when the vacuum gauge 48 has returned to atmospheric pressure, i.e., when the vacuum gauge 48 has returned to approximately psia.
  • the filling process may be automated by utilizing a vacuum switch (not shown) to operate the valves 46 and 50.
  • the switch would keep valve 46 closed and valve 50 opened until a vacuum of 7% to 9 psia, for example, is reached.
  • Valve 50 would then be closed and valve 46 opened until sufficient slurry had entered to substantially eliminate the vacuum at which time valve 46 would be closed.
  • the preferred embodiment includes an essentially solid retainer 24 with a single ring of openings 31 proximate its bottom, the retainer may include several rings of opening 31, or may simply consist of a wire screen cage.
  • the essential feature is that the retainer 24 allows egress of liquid from the chamber 42 without allowing resins to pass therethrough.
  • the injection coupling 21 should include internal threads 53. It will be recalled that the lid 16 also has threads 41. When the injection header 20 is removed, threaded plugs (not shown) should be inserted so as to engage threads 53 and 41 thus forming a double seal to egress of resins.
  • Apparatus for encapsulating a radioactive resinwater waste slurry of the type removed from nuclear reactor power plants comprising:
  • an outer container made of a material which functions as a radioactive shield
  • said inner container being of the same configuration as the drum but of a size substantially less than said drum and having the space between the drum and inner container walls filled with said mixture;
  • said mixture further including a layer overlying the top of said inner container;
  • a pipe extending through said opening and terminating at one end in said inner container and arranged at its other end to be selectively connected to a resin-water slurry source and to a vacuum pump, and valves between said slurry source and pump and said pipe respectively;
  • the means establishing communication with the mixture in said space comprises multiple openings in the base of said inner container for permitting egress of liquid into contact with said mixture in the space.
  • the means defining the opening in the overlying mixture layer comprises a cylindrical injection coupling having threads on its upper end for receiving a plug used to seal the resin-slurry mixture in said drum and container;

Abstract

A device and process wherein a metallic drum is lined with a layer of cement and vermiculite and evacuated. An injection header is fitted to and extends into the hollow interior of the lined drum to permit access of radioactive waste comprising a resin-water slurry. The hollow interior of the drum may fill with resins while the cement-vermiculite layer uniformly absorbs the water therefrom.

Description

United States Patent Kucherer 1 1 July 31,1973
1 1 DEVICE FOR ENCAPSULA'IING A RADIOACTIVE RESIN-WATER SLURRY [76] Inventor: Harvey D. Kucherer, 1321 Foxwood Dr., Monroeville, Pa. 15146 [22] Filed: May 12,1971
[21] Appl. No.: 142,788
Related [1.8. Application Data Continuation-impart of Ser. No. 792,282, Jan. 21, 1969, abandoned.
US. CL..." 250/108 R, 250/106 S, 250/108 FS Int. Cl G21! 9/16, G211" 9/22 Field of Search 250/106 S, 108 WS,
250/108 FS, 108 R; 106/100; 252/3013 References Cited UNITED STATES PATENTS 12/1959 Struxness et al. 250/108 WS [/1968 Karter 252/3011 WS 3/1969 Nash et a1 250/108 R OTHER PUBLlCATlONS Barbour et al.: A. E. Board Report P.E.L. 102; Atomic Energy Board of Republic of South Africa; pages 18; Sec. 1965.
Primary Examiner-James W. Lawrence An0rney-A. '1v Stratton, Z. L. Dermer and M. B. 1,. Hepps [57] ABSTRACT A device and process wherein a metallic drum is lined with a layer of cement and vermiculite and evacuated. An injection header is fitted to and extends into the hol low interior of the lined drum to permit access of radioactive waste comprising a resin-water slurry. The hollow interior of the drum may fill with resins while the cement-vermiculite layer uniformly absorbs the water therefrom.
3 Claims, 1 Drawing Figure BACKGROUND OF THE INVENTION This invention relates to a device and process for the encapsulation of radioactive waste, and more particularly to prepared containers for receiving radioactive resin-water slurries.
The presently preferred technique for packaging radioactive waste materials, particularly those involving resin-water slurries, comprises centrifuging the slurry to dewater the resinous material, mixing the resins with cement in a cement mixer, and allowing this mixture to harden in a drum. The water from the slurry is generally poured into a prepared drum of cement mixed with vermiculite.
In certain reports, i.e. Report P.E.L. 102 issued by the Atomic Energy Board of The Republic of South Africa, it is suggested that the water receiving drum containing the cement-vermiculite mixture be evacuated prior to water ingress. This report indicates that the evacuated mixture absorbs more water, more uniformly, and without wet spots, i.e., areas where the cement is not entirely solidified due to the presence of an excess amount of water.
It should be apparent that present practices involve multiple processes such as dewatering and separate handling of the water and the solid materials, and involves the use of much equipment which is rendered radioactive such as a centrifuge and cement mixer. The above technique further involves substantial expense and some danger to operating personnel.
It is accordingly the object of this invention to encapsulate radioactive resin-water slurries directly thus simplifying the procedure and eliminating much equipment, and to produce a superior encapsulated package.
SUMMARY OF THE INVENTION The direct encapsulation of a radioactive resin-water slurry created for example from mixed bed ion exchanger resins in nuclear power plants is facilitated by providing an evacuated metallic drum which is completely lined with cement on a cement-vermiculite mixture and which includes an injection header or conduit allowing ingress of the slurry to the hollow interior of the container.
A drum is first prepared by placing a layer of cement or cement and vermiculite on its bottom. A cylindrical retainer assembly is then inserted such that an annular layer and a top layer of cement or cement-vermiculite can be poured. Subsequently the conductor injection header extending into the interior of the layers is fitted to the drum and to the lid thereof.
The drum is then evacuated so that air does not inhibit the ingress of the slurry and such that the vacuum produced aids in the uniform dewatering of the resinwater slurry.
Once the resin-water slurry has entered the chamber formed by the cement mixture, the water is drawn into and uniformly dispersed within the mixture. The chamber therefore is substantially free of water and its entire volume may be utilized to store resinous material.
DESCRIPTION OF THE DRAWINGS For a better understanding of the invention reference may be had to the accompanying drawing which shows a container surrounded by a shield and prepared for encapsulating a resin-water slurry.
DESCRIPTION OF THE PREFERRED EMBODIMENT Referring to the drawing, there is shown an encapsulation container 10, in accordance with this invention, surrounded by a shield 12 which may be of lead filled steel, as is known in this art. The container 10 essentially comprises: a drum l4 sealed by a lid 16, both of which may be suitably made of carbon steel; a liner 18 of cement or of a mixture of cement and vermiculite; and an injection header or conduit 20.
The container 10 is preferably prepared as follows:
A mix is prepared which suitably consists of any of the common forms of cement; either alone, or preferably in combination with vermiculite.
A bottom layer 22 of mix is placed in the drum 14. An inner retainer 24 which has an injection coupling 21 fitted thereto is then situated centrally within the drum l4 and is supported on the bottom layer 22. The inner retainer 24 preferably includes a cylindrical side portion 26 and a top 28 and a bottom 30. A plurality of openings 31 are provided in the cylindrical side portion 26 for egress of liquid. The openings 31 are preferably at the bottom of the retainer 24. The remaining volume of the drum l4 exterior to the retainer 24 is filled with the mix. Pins 25 may be provided to aid in maintaining the position of the retainer 24. The drum lid 16 may then be installed and locked to the drum 14 with a common bolted closing ring 32. The lid 16 should have its center contacting and supported by a flange 33 on the injection coupling 21.
When a sufficient amount of radioactive resin-water slurry has been accumulated to fill a container 10, the container 10 is placed within the shield 12. The shield 12 may be most conveniently utilized when comprising two sections; a drum support section 34 and a sleeve section 36 which can be releasably locked to the support section 34, as by pins 35. The injection header 20 is then fitted to the container 10.
The injection header 20 comprises a vacuum header 38 which is open and externally threaded at its bottom, as indicated by the numeral 39, and sealed at its top to a resin-water slurry injection pipe 40, as by welding. The external threads 39 are arranged to engage with threads 41 on the drum lid 16. The pipe 40 extends through the injection coupling 21 into the chamber 42 formed by the liner 18. A vacuum test line 44 is also fitted to the vacuum header 38. The slurry injection pipe 40 has a valve 46 fitted therein, and the vacuum line 44 has a vacuum gauge 48 fitted thereto. The pipe 40 extends to a resin-water slurry hold-up tank (not shown). A vacuum conduit 49 which is connected to vacuum pump (not shown) and which contains a valve 50 is connected to pipe 40 above the vacuum header 38.
To operate the composite structure, valve 46 is closed and valve 50 is opened and the vacuum pump is utilized to evacuate the drum 14 for example 7% to 9 pain for a 30 gallon drum with a 3 inch liner 18. Holes 52 are provided in the flange 33 to assure communication between the evacuated liner l8 and the vacuum header 38. Valve 50 is then closed and valve 46 opened to admit the resin-water slurry to the interior of drum l4.
The resin-water slurry entering through pipe 40 extending a short distance into chamber 42 is prohibited from eroding the bottom layer 22 of the liner 18 by the bottom portion 30 of the retainer 24. The resins accumulate within central chamber 42. The water passes through the holes 31 in the inner retainer 24 and is drawn into the liner 18. The water substantially uniformly wets the entire liner 18 since the vacuum constantly causes the liquid to migrate from relatively filled" regions to unfilled regions, i.e., those still possessing a relatively low pressure due to evacuation. The liner l8 subsequently hardens chemically. Valve 46 is closed when the container 10 is completely full. The "full state" may be ascertained by noting when the vacuum gauge 48 has returned to atmospheric pressure, i.e., when the vacuum gauge 48 has returned to approximately psia.
The filling process may be automated by utilizing a vacuum switch (not shown) to operate the valves 46 and 50. In operation, the switch would keep valve 46 closed and valve 50 opened until a vacuum of 7% to 9 psia, for example, is reached. Valve 50 would then be closed and valve 46 opened until sufficient slurry had entered to substantially eliminate the vacuum at which time valve 46 would be closed.
Although the preferred embodiment includes an essentially solid retainer 24 with a single ring of openings 31 proximate its bottom, the retainer may include several rings of opening 31, or may simply consist of a wire screen cage. The essential feature is that the retainer 24 allows egress of liquid from the chamber 42 without allowing resins to pass therethrough.
The injection coupling 21 should include internal threads 53. It will be recalled that the lid 16 also has threads 41. When the injection header 20 is removed, threaded plugs (not shown) should be inserted so as to engage threads 53 and 41 thus forming a double seal to egress of resins.
While there has been shown and described what is considered to be the preferred embodiment of the invention, modifications thereto will occur to those skilled in the art. The container 10 could also be utilized for slurries which has little or no resin content simply by reducing the size of chamber 42 and optionally filling chamber 42 with vermiculite. Accordingly, it is not desired that the invention be limited to the specific arrangement described but rather that the true scope of the invention be delineated in the appended claims.
What is claimed is:
1. Apparatus for encapsulating a radioactive resinwater waste slurry of the type removed from nuclear reactor power plants comprising:
an outer container made of a material which functions as a radioactive shield;
a drum having a closable lid in said outer container;
a dry mixture of construction cement and vermiculite in the base of said drum;
a closed inner container in said drum, said inner container being of the same configuration as the drum but of a size substantially less than said drum and having the space between the drum and inner container walls filled with said mixture;
said mixture further including a layer overlying the top of said inner container;
means in said inner container establishing communication between said container and the mixture in said space;
means extending from the inner container through the overlying layer and the drum lid which defines an opening;
a pipe extending through said opening and terminating at one end in said inner container and arranged at its other end to be selectively connected to a resin-water slurry source and to a vacuum pump, and valves between said slurry source and pump and said pipe respectively;
whereby upon evacuating said inner container of air, the resin-water slurry is caused to flow into the inner container, the water therein gravitating through the means in the container into contact with said mixture in the space which later forms a solid mass while the solid particles in the slurry remain in the container.
2. The apparatus according to claim 1 wherein the means establishing communication with the mixture in said space comprises multiple openings in the base of said inner container for permitting egress of liquid into contact with said mixture in the space.
3. The apparatus according to claim 1 wherein the means defining the opening in the overlying mixture layer comprises a cylindrical injection coupling having threads on its upper end for receiving a plug used to seal the resin-slurry mixture in said drum and container; and
a vacuum header coupled to said lid and overlying said opening, and wherein said pipe extends through the vacuum header and said opening. 4 k 4

Claims (2)

  1. 2. The apparatus according to claim 1 wherein the means establishing communication with the mixture in said space comprises multiple openings in the base of said inner container for permitting egress of liquid into contact with said mixture in the space.
  2. 3. The apparatus according to claim 1 wherein the means defining the opening in the oVerlying mixture layer comprises a cylindrical injection coupling having threads on its upper end for receiving a plug used to seal the resin-slurry mixture in said drum and container; and a vacuum header coupled to said lid and overlying said opening, and wherein said pipe extends through the vacuum header and said opening.
US00142788A 1971-05-12 1971-05-12 Device for encapsulating a radioactive resin-water slurry Expired - Lifetime US3749917A (en)

Applications Claiming Priority (1)

Application Number Priority Date Filing Date Title
US14278871A 1971-05-12 1971-05-12

Publications (1)

Publication Number Publication Date
US3749917A true US3749917A (en) 1973-07-31

Family

ID=22501281

Family Applications (1)

Application Number Title Priority Date Filing Date
US00142788A Expired - Lifetime US3749917A (en) 1971-05-12 1971-05-12 Device for encapsulating a radioactive resin-water slurry

Country Status (1)

Country Link
US (1) US3749917A (en)

Cited By (24)

* Cited by examiner, † Cited by third party
Publication number Priority date Publication date Assignee Title
FR2231079A1 (en) * 1973-05-25 1974-12-20 Cnen
US3940628A (en) * 1971-09-20 1976-02-24 Stock Equipment Company Apparatus and process for handling dangerous fluent material
US3982134A (en) * 1974-03-01 1976-09-21 Housholder William R Shipping container for nuclear fuels
US4229316A (en) * 1978-02-03 1980-10-21 Steag Kernenergie Gmbh Device for the storage or disposal of radioactive wastes
US4422964A (en) * 1981-11-30 1983-12-27 Capolupo & Gundal, Inc. Radioactive waste container with immobilization compartment and method
EP0143212A1 (en) * 1983-09-03 1985-06-05 Forschungszentrum Jülich Gmbh Container for transporting and storing radioactive materials
US4582638A (en) * 1981-03-27 1986-04-15 General Signal Corporation Method and means for disposal of radioactive waste
US4594513A (en) * 1982-11-08 1986-06-10 Chichibu Cement Co., Ltd. Multiplex design container having a three-layered wall structure and a process for producing the same
US4610839A (en) * 1982-12-24 1986-09-09 Nukem Gmbh Storage container and carrying peg for radioactive material
US4666676A (en) * 1985-08-30 1987-05-19 The United States Of America As Represented By The United States Department Of Energy Radioactive waste processing apparatus
US4717510A (en) * 1983-08-02 1988-01-05 United Kingdom Atomic Energy Authority Encapsulation of waste material
US4749520A (en) * 1985-04-16 1988-06-07 Kraftwerk Union Aktiengesellschaft Method for producing casks capable of ultimate storage with radioactive waste, and cask produced in accordance with this method
US4842773A (en) * 1986-12-17 1989-06-27 Deutsche Gesellschaft Fur Wiederaufarbeitung Von Kernbrennstoffen Mbh Method of producing a solid product containing cement for storing tritium water in an accessible terminal storage facility
US4904416A (en) * 1987-05-21 1990-02-27 Kyushu Electric Power Co., Ltd. Cement solidification treatment of spent ion exchange resins
US4983282A (en) * 1988-12-12 1991-01-08 Westinghouse Electric Corp. Apparatus for removing liquid from a composition and for storing the deliquified composition
US5022995A (en) * 1989-11-16 1991-06-11 Westinghouse Electric Corp. Apparatus and method for removing liquid from a composition and for storing the deliquified composition
FR2662295A1 (en) * 1990-05-18 1991-11-22 Commissariat Energie Atomique CONTAINER DEVICE FOR STORING RADIOACTIVE OR TOXIC WASTE, AND FILLING METHOD THEREFOR.
US5100586A (en) * 1990-07-20 1992-03-31 E. Khashoggi Industries Cementitious hazardous waste containers and their method of manufacture
US5169566A (en) * 1990-05-18 1992-12-08 E. Khashoggi Industries Engineered cementitious contaminant barriers and their method of manufacture
WO1993012526A1 (en) * 1990-11-16 1993-06-24 Alternative Technologies For Waste, Inc. Biaxial casting method and apparatus for isolating radioactive waste
US5227060A (en) * 1989-11-16 1993-07-13 Westinghouse Electric Corp. Apparatus and method for removing liquid from a composition and for storing the deliquified composition
US20090134346A1 (en) * 2005-09-07 2009-05-28 Hallvar Eide Container and method and device for manufacturing of such containers
US20090224171A1 (en) * 2006-07-06 2009-09-10 Verbokkem Arjan F System and Method for Controlling Elution from a Radioisotope Generator with Electronic Pinch Valves
CN108081460A (en) * 2017-12-14 2018-05-29 东莞理工学院 A kind of collocation mechanism of radiation shield concrete slurry for neutron research

Citations (3)

* Cited by examiner, † Cited by third party
Publication number Priority date Publication date Assignee Title
US2918717A (en) * 1956-12-12 1959-12-29 Edward G Struxness Self sintering of radioactive wastes
US3361649A (en) * 1965-04-05 1968-01-02 American Mach & Foundry Method and apparatus for distillation of waste liquids and separate recovery of solvent and solute
US3432666A (en) * 1964-03-13 1969-03-11 Atomic Energy Authority Uk Containers for transporting radioactive and/or fissile materials

Patent Citations (3)

* Cited by examiner, † Cited by third party
Publication number Priority date Publication date Assignee Title
US2918717A (en) * 1956-12-12 1959-12-29 Edward G Struxness Self sintering of radioactive wastes
US3432666A (en) * 1964-03-13 1969-03-11 Atomic Energy Authority Uk Containers for transporting radioactive and/or fissile materials
US3361649A (en) * 1965-04-05 1968-01-02 American Mach & Foundry Method and apparatus for distillation of waste liquids and separate recovery of solvent and solute

Non-Patent Citations (1)

* Cited by examiner, † Cited by third party
Title
Barbour et al.: A. E. Board Report P.E.L. 102; Atomic Energy Board of Republic of South Africa; pages 1 8; Sec. 1965. *

Cited By (26)

* Cited by examiner, † Cited by third party
Publication number Priority date Publication date Assignee Title
US3940628A (en) * 1971-09-20 1976-02-24 Stock Equipment Company Apparatus and process for handling dangerous fluent material
FR2231079A1 (en) * 1973-05-25 1974-12-20 Cnen
US3982134A (en) * 1974-03-01 1976-09-21 Housholder William R Shipping container for nuclear fuels
US4229316A (en) * 1978-02-03 1980-10-21 Steag Kernenergie Gmbh Device for the storage or disposal of radioactive wastes
US4582638A (en) * 1981-03-27 1986-04-15 General Signal Corporation Method and means for disposal of radioactive waste
US4422964A (en) * 1981-11-30 1983-12-27 Capolupo & Gundal, Inc. Radioactive waste container with immobilization compartment and method
US4594513A (en) * 1982-11-08 1986-06-10 Chichibu Cement Co., Ltd. Multiplex design container having a three-layered wall structure and a process for producing the same
US4610839A (en) * 1982-12-24 1986-09-09 Nukem Gmbh Storage container and carrying peg for radioactive material
US4717510A (en) * 1983-08-02 1988-01-05 United Kingdom Atomic Energy Authority Encapsulation of waste material
EP0143212A1 (en) * 1983-09-03 1985-06-05 Forschungszentrum Jülich Gmbh Container for transporting and storing radioactive materials
US4749520A (en) * 1985-04-16 1988-06-07 Kraftwerk Union Aktiengesellschaft Method for producing casks capable of ultimate storage with radioactive waste, and cask produced in accordance with this method
US4666676A (en) * 1985-08-30 1987-05-19 The United States Of America As Represented By The United States Department Of Energy Radioactive waste processing apparatus
US4842773A (en) * 1986-12-17 1989-06-27 Deutsche Gesellschaft Fur Wiederaufarbeitung Von Kernbrennstoffen Mbh Method of producing a solid product containing cement for storing tritium water in an accessible terminal storage facility
US4904416A (en) * 1987-05-21 1990-02-27 Kyushu Electric Power Co., Ltd. Cement solidification treatment of spent ion exchange resins
US4983282A (en) * 1988-12-12 1991-01-08 Westinghouse Electric Corp. Apparatus for removing liquid from a composition and for storing the deliquified composition
US5022995A (en) * 1989-11-16 1991-06-11 Westinghouse Electric Corp. Apparatus and method for removing liquid from a composition and for storing the deliquified composition
US5227060A (en) * 1989-11-16 1993-07-13 Westinghouse Electric Corp. Apparatus and method for removing liquid from a composition and for storing the deliquified composition
US5169566A (en) * 1990-05-18 1992-12-08 E. Khashoggi Industries Engineered cementitious contaminant barriers and their method of manufacture
EP0458682A1 (en) * 1990-05-18 1991-11-27 Commissariat A L'energie Atomique Equipment or storing container for radio-active or toxic wastes, and its filling process
FR2662295A1 (en) * 1990-05-18 1991-11-22 Commissariat Energie Atomique CONTAINER DEVICE FOR STORING RADIOACTIVE OR TOXIC WASTE, AND FILLING METHOD THEREFOR.
US5100586A (en) * 1990-07-20 1992-03-31 E. Khashoggi Industries Cementitious hazardous waste containers and their method of manufacture
WO1993012526A1 (en) * 1990-11-16 1993-06-24 Alternative Technologies For Waste, Inc. Biaxial casting method and apparatus for isolating radioactive waste
US20090134346A1 (en) * 2005-09-07 2009-05-28 Hallvar Eide Container and method and device for manufacturing of such containers
US20090224171A1 (en) * 2006-07-06 2009-09-10 Verbokkem Arjan F System and Method for Controlling Elution from a Radioisotope Generator with Electronic Pinch Valves
CN108081460A (en) * 2017-12-14 2018-05-29 东莞理工学院 A kind of collocation mechanism of radiation shield concrete slurry for neutron research
CN108081460B (en) * 2017-12-14 2019-06-07 东莞理工学院 A kind of collocation mechanism of the radiation shield concrete slurry for neutron research

Similar Documents

Publication Publication Date Title
US3749917A (en) Device for encapsulating a radioactive resin-water slurry
US3658179A (en) Method for separating liquid from solid substances and storing the solid substances
US4234798A (en) Transport and storage receptacle for radioactive waste
US4229316A (en) Device for the storage or disposal of radioactive wastes
CN103345955B (en) In, low-activity nuclear waste disposal apparatus
US4424903A (en) Apparatus for storing tritium, especially tritium wastes from nuclear power plants
US4675129A (en) Method of handling radioactive waste and especially radioactive or radioactively contaminated evaporator concentrates and water-containing solids
US4235739A (en) Canister method of disposing of radioactive waste
DE2001936A1 (en) Device for the radiation-safe reception of radioactive waste
US4629587A (en) Solidifying disposal system for radioactive waste
US5008045A (en) Method and apparatus for centrifugally casting hazardous waste
DE2726335A1 (en) FINAL STORAGE CONTAINER FOR RADIOACTIVE WASTE
US3983050A (en) Method for storage of solid waste
GB2148584A (en) Waste material particularly radioactive waste material
US3324540A (en) Method for making porous target pellets for a nuclear reactor
CN206116028U (en) Spentnuclear fuel dry -type shielding container
US5043103A (en) Method and apparatus for centrifugally casting hazardous waste
US3965359A (en) Irradiation plant having a common closure
US3848423A (en) Handling system for nuclear fuel assemblies
US3749370A (en) Mixing device for powdered materials
CN1025259C (en) Storage container for radio-active wastes
RU2724966C1 (en) Container for radioactive wastes
JPH0421159B2 (en)
CA1111807A (en) Introduction of fluent materials into containers
RU2154316C2 (en) Container for storage and transport of spent fuel assemblies