US3466662A - Fireproof shielded containers for radioactive materials - Google Patents

Fireproof shielded containers for radioactive materials Download PDF

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US3466662A
US3466662A US494697A US49469765A US3466662A US 3466662 A US3466662 A US 3466662A US 494697 A US494697 A US 494697A US 49469765 A US49469765 A US 49469765A US 3466662 A US3466662 A US 3466662A
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screen
lead
container
radioactive materials
calcium sulphate
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US494697A
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Paul Blum
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LYONNAISE DE PLOMBERIE IND SOC
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LYONNAISE DE PLOMBERIE IND SOC
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    • 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
    • G21F5/00—Transportable or portable shielded containers
    • G21F5/005—Containers for solid radioactive wastes, e.g. for ultimate disposal

Definitions

  • a container for radio-active materials of the kind comprising an inner casing, a lead screen closely surrounding this casing and an outer shell, as for instance of steel, there is left between the lead screen and the outer shell an intermediate space which is lled with plaster (hydrated calcium sulphate) to form a refractory protective heat-insulating and water containing layer.
  • the cover of the container may also comprise a layer of plaster between its lead screen and its outer plate.
  • This invention refers to containers for radioactive materials.
  • Radioactive materials are generally stored and transported within containers so arranged as to protect against dangerous radiations.
  • the casing in which the material is disposed is generally surrounded by a thick lead screen which is itself re-inforced by an outer metallic shell.
  • the devices or casks thus realized may be damaged by violet shocks or by tire and therefore they are generally placed within another protective casing made of wood or like relatively deformable material and having an outer metallic covering.
  • the present invention has for its object to provide a container for radio-active materials which will not suffer from the above inconveniences.
  • a container for radioactive materials comprises an inner casing, a thick lead screen surrounding the said casing in direct contact therewith, an outer shell surrounding the lead screen, but of such dimensions as to leave an intermediate space, and a mass of plaster, i.e., hydrated calcium sulphate (SO4Ca, 11H20) poured into the said intermediate space to lill the same.
  • plaster i.e., hydrated calcium sulphate (SO4Ca, 11H20)
  • the mechanical and the thermal characteristics of the mass which tills the intermediate space may be varied at will by incorporating to the calcium sulphate appropriate llers.
  • the llers are preferably of heat-insulating character. With containers of large dimensions in which the radioactive material may generate an important quantity of heat, it may on the contrary be desirable to use heat-conducting llers.
  • the mass of hydrated calcium sulphate contains a considerable quantity of water. In the case of a re this water is liberated in the form of steam. In order to avoid bursting of the outer shell the latter is preferably provided with vents which are normally closed by readily frangible covers or by easily fusible plugs. This generation of steam absorbs a considerable quantity of heat, but even when the whole mass is fully dehydrated, it still forms an excellent heat insulating layer.
  • FIG. 1 is a fragmental vertical section of a container according to the present invention.
  • FIGS. 2 and 3 are small scale views which diagrammatically illustrate two steps during the manufacture of the container.
  • the container illustrated in FIG. l comprises an inner casing 1 of conventional type, adapted to house the radioactive material to be transported.
  • the upper end of this inner casing is closed by a removable cover 2, seals 3 being disposed below the underface of the cover and a flanged portion of the wall of the casing.
  • a thick lead screen 4 surrounds the inner casing 1 in direct contact with the outer surface thereof.
  • the cover 2 is provided with an upturned lateral edge and it has also a thick lead layer or screen S on its upper face.
  • the upturned upper edge of the inner casing 1 is counected with an upper horizontal flange 6 by an upwardly flaring frusto-conical intermediate annular portion 7, preferably made of stainless steel, which may be welded to the said edge and to the flange.
  • This intermediate portion is wide enough to provide a substantial space between the outer surface of the lead screen 4 and the flange 6.
  • the flange 6 is itself welded to an outer metallic shell 8 of such dimensions as to leave an intermediate space between its inner surface and the outer surface of the lead screen 4.
  • the outer edge of the cover 2 is similarly connected with an outer horizontal flange 9 by an intermediate frusto-conical portion 10 made of stainless steel, the said ange 9 being welded with an upper plate 11 spaced from the upper surface of the lead layer or screen S.
  • the intermediate space comprised -between the lead screen 4 and the outer shell 8 is lled with a mass 13 of hydrated calcium sulphate I(plaster) which has -been obtained by pouring this substance into the said space in the liquid or semi-liquid state.
  • the space between the lead layer 5 and the upper plate 11 is similarlyjilled with another mass 13 of hydrated calcium sulphate.
  • the ilanges 6 and 9 are provided with appropriate passages or vents which are normally obturated by fusible plugs such as 14 and 15.
  • the outer shell 8 may further comprise easily fragnible portions or fusible discs, such as 16.
  • FIGS. 2 and 3 illustrate the manufacturing step of a container according to the present invention.
  • the inner casing 1 made for instance of stainless sheet-iron, is disposed in the inverted position on an appropriate supporting surface, not illustrated.
  • a tubular open-ended mould 17 is then placed on the casing with its intumed lower edge resting on the intermediate frustoconical portion 7 of the casing.
  • Molten lead is poured linto the inner space A of the mould to form the lead screen around the casing.
  • the mold is removed and the screen thus obtained is machined to the exact configuration desired.
  • the outer shell 8 has been prepared separately with apertures such as 8a in its bottom. It is disposed at the inverted position on the unit formed by the inner casing and the lead screen, and the horizontal flange 6 is welded to the intermediate portion 7 and to the edge of the open end of the outer shell 8. Alternatively this flange could have been previously welded to the intermediate portion 7 before casting the lead screen, if desired. In any case this horizontal flange 6 acts as a centering means for the outer shell 8 with respect to the inner casing 1.
  • the apertures 8a are closed by means of fusible discs such as 16 (FIG. l).
  • the cover of the container is prepared in the same manner, but here the upturned lateral edge of the cover forms the mould into which the molten lead is poured to form the layer or screen 5.
  • the upper plate 11 is formed with apertures, not shown, through which the mass of calcium sulphate may be poured after the plate is welded to the outer fiange 9. As in the case of the apertures 8a of the outer shell 8, these apertures of the upperplate are thereafter closed by fusible discs.
  • an open-ended container for radioactive materials comprising an inner casing, a protective lead screen surrounding said inner casing in direct contact therewith,
  • a container as claimed in claim 1 further having a cover to close its upper end with said cover having an inner plate with an inner side and an outer side, a protective lead layer in contact with the outer side of said plate, an outer plate to cover said lead layer, and flange means to connect said inner plate with said outer plate, the improvement in which said outer plate is spaced from said screen layer to define therewith an intermediate space, said cover further comprising a solid non-shielding mass of hydrated calcium sulphate filling said intermediate space between said inner and outer plates to form a heat-absorbing barrier protecting said lead layer against fires.

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  • Physics & Mathematics (AREA)
  • Engineering & Computer Science (AREA)
  • General Engineering & Computer Science (AREA)
  • High Energy & Nuclear Physics (AREA)
  • Packages (AREA)
  • Pressure Vessels And Lids Thereof (AREA)

Description

P. BLUM Sept. 9, 1969 FIREPROOF SHIELDED CONTAINERS FOR RADIOACTIVE MATERIALS Filed Oct. l1. 1965 United States Patent 3,466,662 FIREPROOF SHIELDED CONTAINERS FOR RADIOACTIVE MATERIALS Paul Blum, Saint-Genis-Laval, France, assgnor to Societe Lyonnaise de Plomberie Industrielle, Lyon (Rhone), France, a joint-stock company of France Filed Oct. 11, 1965, Ser. No. 494,697 Claims priority, application France, Oct. 21, 1964, 4 ,242 Int. Cl. G21h 5/00 U.S. Cl. 250--106 4 Claims ABSTRACT 0F THE DISCLSURE In a container for radio-active materials, of the kind comprising an inner casing, a lead screen closely surrounding this casing and an outer shell, as for instance of steel, there is left between the lead screen and the outer shell an intermediate space which is lled with plaster (hydrated calcium sulphate) to form a refractory protective heat-insulating and water containing layer. The cover of the container may also comprise a layer of plaster between its lead screen and its outer plate.
This invention refers to containers for radioactive materials.
Radioactive materials are generally stored and transported within containers so arranged as to protect against dangerous radiations. For this purpose the casing in which the material is disposed, is generally surrounded by a thick lead screen which is itself re-inforced by an outer metallic shell. But the devices or casks thus realized may be damaged by violet shocks or by tire and therefore they are generally placed within another protective casing made of wood or like relatively deformable material and having an outer metallic covering.
These containers are relatively expensive, their decontamination is difficult. When the radioactive material generates an important quantity of heat, the latter is not easily dissipated through the container walls and therefore the inner temperature rises undesrably.
The present invention has for its object to provide a container for radio-active materials which will not suffer from the above inconveniences.
In accordance with the present invention a container for radioactive materials comprises an inner casing, a thick lead screen surrounding the said casing in direct contact therewith, an outer shell surrounding the lead screen, but of such dimensions as to leave an intermediate space, and a mass of plaster, i.e., hydrated calcium sulphate (SO4Ca, 11H20) poured into the said intermediate space to lill the same.
When the calcium sulphate sets, its volume increases and its mass is therefore applied under a considerable pressure against the lead screen and against the outer shell. There is thus obtained an eflicient bonding between the shell and the screen. This increases the mechanical strength of the container and improves heat conductivity.
It is to be noted that the mechanical and the thermal characteristics of the mass which tills the intermediate space may be varied at will by incorporating to the calcium sulphate appropriate llers. In the case of containers of small dimensions in which the heat generated by the radioactive material is negligible, the llers are preferably of heat-insulating character. With containers of large dimensions in which the radioactive material may generate an important quantity of heat, it may on the contrary be desirable to use heat-conducting llers. The
3,466,662 Patented Sept. 9, 1969 c ICC llers may besides improve the mechanical characteristics of the calcium sulphate mass. Such is the case for instance with llers of fibrous character, as for instance glass libres, asbestos, wood libres, or the like. Vermiculite may be used with advantage as a heat-insulating iiller, while metal chips or metallic powders may increase heat conductivity.
The mass of hydrated calcium sulphate contains a considerable quantity of water. In the case of a re this water is liberated in the form of steam. In order to avoid bursting of the outer shell the latter is preferably provided with vents which are normally closed by readily frangible covers or by easily fusible plugs. This generation of steam absorbs a considerable quantity of heat, but even when the whole mass is fully dehydrated, it still forms an excellent heat insulating layer.
In the accompanying drawings:
FIG. 1 is a fragmental vertical section of a container according to the present invention.
FIGS. 2 and 3 are small scale views which diagrammatically illustrate two steps during the manufacture of the container.
The container illustrated in FIG. l comprises an inner casing 1 of conventional type, adapted to house the radioactive material to be transported. The upper end of this inner casing is closed by a removable cover 2, seals 3 being disposed below the underface of the cover and a flanged portion of the wall of the casing. A thick lead screen 4 surrounds the inner casing 1 in direct contact with the outer surface thereof. The cover 2 is provided with an upturned lateral edge and it has also a thick lead layer or screen S on its upper face.
The upturned upper edge of the inner casing 1 is counected with an upper horizontal flange 6 by an upwardly flaring frusto-conical intermediate annular portion 7, preferably made of stainless steel, which may be welded to the said edge and to the flange. This intermediate portion is wide enough to provide a substantial space between the outer surface of the lead screen 4 and the flange 6. The flange 6 is itself welded to an outer metallic shell 8 of such dimensions as to leave an intermediate space between its inner surface and the outer surface of the lead screen 4. The outer edge of the cover 2 is similarly connected with an outer horizontal flange 9 by an intermediate frusto-conical portion 10 made of stainless steel, the said ange 9 being welded with an upper plate 11 spaced from the upper surface of the lead layer or screen S.
The anges 6 and 9 of the container and of its cover are assembled by means of screws 12.
The intermediate space comprised -between the lead screen 4 and the outer shell 8 is lled with a mass 13 of hydrated calcium sulphate I(plaster) which has -been obtained by pouring this substance into the said space in the liquid or semi-liquid state. Also the space between the lead layer 5 and the upper plate 11 is similarlyjilled with another mass 13 of hydrated calcium sulphate. These masses 13, 13' connstitute a lire-proof layer which protects the lead screens 4 and 5 and they strongly bond the outer walls of the container, i.e., the shell 8 and the plate 11, with the said screens. Further owing to the large quantity of water which they contain, they may absorb a considerable quantity of heat at a relatively moderate temperature. In order to permit free exhaust of the steam which would then be generated within the hydrated sulphate, the ilanges 6 and 9 are provided with appropriate passages or vents which are normally obturated by fusible plugs such as 14 and 15. The outer shell 8 may further comprise easily fragnible portions or fusible discs, such as 16.
FIGS. 2 and 3 illustrate the manufacturing step of a container according to the present invention. As shown in FIG. 2 the inner casing 1, made for instance of stainless sheet-iron, is disposed in the inverted position on an appropriate supporting surface, not illustrated. A tubular open-ended mould 17 is then placed on the casing with its intumed lower edge resting on the intermediate frustoconical portion 7 of the casing. Molten lead is poured linto the inner space A of the mould to form the lead screen around the casing. When the lead is solidified, the mold is removed and the screen thus obtained is machined to the exact configuration desired.
The outer shell 8 has been prepared separately with apertures such as 8a in its bottom. It is disposed at the inverted position on the unit formed by the inner casing and the lead screen, and the horizontal flange 6 is welded to the intermediate portion 7 and to the edge of the open end of the outer shell 8. Alternatively this flange could have been previously welded to the intermediate portion 7 before casting the lead screen, if desired. In any case this horizontal flange 6 acts as a centering means for the outer shell 8 with respect to the inner casing 1. A liquid `or semi-liquid mass of hydrated calcium sulphate, or more evactly of anhydrous calcium sulphate mixed with water, is then poured into the intermediate space B delimited by the outer surface of the lead screen 4, the intermediate annular portion 7, the horizontal flange 6 and the outer shell 8. When this mass has set, the apertures 8a are closed by means of fusible discs such as 16 (FIG. l).
The cover of the container is prepared in the same manner, but here the upturned lateral edge of the cover forms the mould into which the molten lead is poured to form the layer or screen 5. The upper plate 11 is formed with apertures, not shown, through which the mass of calcium sulphate may be poured after the plate is welded to the outer fiange 9. As in the case of the apertures 8a of the outer shell 8, these apertures of the upperplate are thereafter closed by fusible discs.
I claim:
1. In an open-ended container for radioactive materials comprising an inner casing, a protective lead screen surrounding said inner casing in direct contact therewith,
an outer shell surrounding said screen, and flange means to connect said outer shell with said inner casing, the improvement in which said outer shell is spaced from said screen to define therewith an intermediate space, said container further comprising a solid non-shielding mass of hydrated calcium sulphate filling said intermediate space to form a heat-absorbing barrier protecting said screen against fires.
2. In a container as claimed in claim 1, further having a cover to close its upper end with said cover having an inner plate with an inner side and an outer side, a protective lead layer in contact with the outer side of said plate, an outer plate to cover said lead layer, and flange means to connect said inner plate with said outer plate, the improvement in which said outer plate is spaced from said screen layer to define therewith an intermediate space, said cover further comprising a solid non-shielding mass of hydrated calcium sulphate filling said intermediate space between said inner and outer plates to form a heat-absorbing barrier protecting said lead layer against fires.
3. In a container as claimed in claim 1, vent means on said outer shell to permit exhaust of steam from said solid -mass of hydrated calcium sulphate.
4. In a container as claimed in claim 2, vent means on said outer plate to permit exhaust of steam from said solid layer of hydrated calcium sulphate.
References Cited UNITED STATES PATENTS 3,005,105 10/1961 Lusk Z50-106 X 3,111,586 11/1963 Rogers Z50-106 X 3,113,215 12/1963 Allen 250--106 X 3,173,884 3/1965 Jackson Z50-108 X RALPH G. NILSON, Primary Examiner A. B. CROFT, Assistant Examiner U.S. Cl. X.R. 220-9; Z50-108
US494697A 1964-10-21 1965-10-11 Fireproof shielded containers for radioactive materials Expired - Lifetime US3466662A (en)

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FR45242A FR1438241A (en) 1964-10-21 1964-10-21 Improvements to caissons or châteaux for the transport of radioactive materials and the like

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GB (1) GB1046848A (en)
NL (1) NL6514374A (en)

Cited By (13)

* Cited by examiner, † Cited by third party
Publication number Priority date Publication date Assignee Title
US3723742A (en) * 1968-04-11 1973-03-27 Trw Inc Radioisotope capsule protection structure
US3780306A (en) * 1971-05-27 1973-12-18 Nat Lead Co Radioactive shipping container with neutron and gamma absorbers
US3886368A (en) * 1973-02-27 1975-05-27 Nuclear Fuel Services Spent fuel shipping cask
US3930166A (en) * 1972-11-28 1975-12-30 Robatel Slpi Package for transporting or enclosing radioactive materials
US3982134A (en) * 1974-03-01 1976-09-21 Housholder William R Shipping container for nuclear fuels
US4747512A (en) * 1987-06-19 1988-05-31 Lo Kin K Transportation packaging for liquids
US5337917A (en) * 1991-10-21 1994-08-16 Sandia Corporation Crash resistant container
WO2006043826A1 (en) * 2004-10-19 2006-04-27 Nuclear Protection Products As Container for long-term storage of radioactive material, and method and apparatus for manufacturing the container
WO2010104398A1 (en) * 2009-03-11 2010-09-16 Nuclear Protection Products As A method and a moulding plant for manufacturing a storage container for storage of nuclear radiation material
US20100284778A1 (en) * 2007-12-26 2010-11-11 Areva Np Transport Container for Nuclear Fuel Assembly and Method of Transporting a Nuclear Fuel Assembly
US8616404B1 (en) * 2010-06-03 2013-12-31 Savannah River Nuclear Solutions, Llc Shipping container
EP2827336A1 (en) * 2013-07-15 2015-01-21 GNS Gesellschaft für Nuklear-Service mbH Transport and/or storage container
US11342091B2 (en) * 2004-03-18 2022-05-24 Holtec International Systems and methods for storing spent nuclear fuel

Families Citing this family (5)

* Cited by examiner, † Cited by third party
Publication number Priority date Publication date Assignee Title
FR2055761A1 (en) * 1969-08-12 1971-04-30 Robatel Slpi
FR2055982A5 (en) * 1969-08-13 1971-05-14 Transnucleaire Storage and transport container for a - radioactive materials
JPS5985999A (en) * 1982-11-08 1984-05-18 秩父セメント株式会社 Multiple container and its manufacture
DE8809283U1 (en) * 1988-07-20 1988-09-22 Nukem GmbH, 63755 Alzenau Transport and/or storage containers for radioactive substances
DE102016108947A1 (en) * 2016-05-13 2017-11-16 Daher Nuclear Technologies Gmbh Arrangement for the transport of radioactive material and method for increasing the fire protection of such an arrangement

Citations (4)

* Cited by examiner, † Cited by third party
Publication number Priority date Publication date Assignee Title
US3005105A (en) * 1958-10-17 1961-10-17 Edlow Lead Company Shipping cask for radioactive materials
US3111586A (en) * 1961-08-25 1963-11-19 Baldwin Lima Hamilton Corp Air-cooled shipping container for nuclear fuel elements
US3113215A (en) * 1961-02-27 1963-12-03 Stanray Corp Cask construction for radioactive material
US3173884A (en) * 1962-07-13 1965-03-16 David A Jackson Concrete comprising galena ore aggregate, calcium aluminum hydraulic binder and standard aggregates

Patent Citations (4)

* Cited by examiner, † Cited by third party
Publication number Priority date Publication date Assignee Title
US3005105A (en) * 1958-10-17 1961-10-17 Edlow Lead Company Shipping cask for radioactive materials
US3113215A (en) * 1961-02-27 1963-12-03 Stanray Corp Cask construction for radioactive material
US3111586A (en) * 1961-08-25 1963-11-19 Baldwin Lima Hamilton Corp Air-cooled shipping container for nuclear fuel elements
US3173884A (en) * 1962-07-13 1965-03-16 David A Jackson Concrete comprising galena ore aggregate, calcium aluminum hydraulic binder and standard aggregates

Cited By (21)

* Cited by examiner, † Cited by third party
Publication number Priority date Publication date Assignee Title
US3723742A (en) * 1968-04-11 1973-03-27 Trw Inc Radioisotope capsule protection structure
US3780306A (en) * 1971-05-27 1973-12-18 Nat Lead Co Radioactive shipping container with neutron and gamma absorbers
US3930166A (en) * 1972-11-28 1975-12-30 Robatel Slpi Package for transporting or enclosing radioactive materials
US3886368A (en) * 1973-02-27 1975-05-27 Nuclear Fuel Services Spent fuel shipping cask
US3982134A (en) * 1974-03-01 1976-09-21 Housholder William R Shipping container for nuclear fuels
US4747512A (en) * 1987-06-19 1988-05-31 Lo Kin K Transportation packaging for liquids
US5337917A (en) * 1991-10-21 1994-08-16 Sandia Corporation Crash resistant container
US11342091B2 (en) * 2004-03-18 2022-05-24 Holtec International Systems and methods for storing spent nuclear fuel
US7741628B2 (en) 2004-10-19 2010-06-22 Nuclear Protection Products As Container for long-term storage of radioactive material, and method and apparatus for manufacturing the container
US20080277602A1 (en) * 2004-10-19 2008-11-13 Frank Stengrimsen Container for Long-Term Storage of Radioactive Material, and Method and Apparatus for Manufacturing the Container
US20080179550A1 (en) * 2004-10-19 2008-07-31 Nuclear Protection Products As Long term storage container and manufacturing method
NO338856B1 (en) * 2004-10-19 2016-10-24 Mezonic As Process for manufacturing container for long-term storage of radioactive material, storage container and casting device for manufacture of container parts
WO2006043826A1 (en) * 2004-10-19 2006-04-27 Nuclear Protection Products As Container for long-term storage of radioactive material, and method and apparatus for manufacturing the container
US20100284778A1 (en) * 2007-12-26 2010-11-11 Areva Np Transport Container for Nuclear Fuel Assembly and Method of Transporting a Nuclear Fuel Assembly
US9275768B2 (en) * 2007-12-26 2016-03-01 Areva Np Transport container for nuclear fuel assembly and method of transporting a nuclear fuel assembly
WO2010104398A1 (en) * 2009-03-11 2010-09-16 Nuclear Protection Products As A method and a moulding plant for manufacturing a storage container for storage of nuclear radiation material
US20100230854A1 (en) * 2009-03-11 2010-09-16 Frank Stengrimsen Method and a plant for manufacturing a storage container for storage of nuclear radiation material
US7981344B2 (en) 2009-03-11 2011-07-19 Nuclear Protection Products As Method for manufacturing a storage container for storage of nuclear radiation material
US8226403B2 (en) 2009-03-11 2012-07-24 Nuclear Protection Products As Moulding apparatus for manufacturing a storage container for storage of nuclear radiation material
US8616404B1 (en) * 2010-06-03 2013-12-31 Savannah River Nuclear Solutions, Llc Shipping container
EP2827336A1 (en) * 2013-07-15 2015-01-21 GNS Gesellschaft für Nuklear-Service mbH Transport and/or storage container

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FR1438241A (en) 1966-05-13
DE1514616A1 (en) 1969-10-02
BE670734A (en) 1966-01-31
NL6514374A (en) 1967-05-08
GB1046848A (en) 1966-10-26

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