US3930166A - Package for transporting or enclosing radioactive materials - Google Patents

Package for transporting or enclosing radioactive materials Download PDF

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US3930166A
US3930166A US424720A US42472073A US3930166A US 3930166 A US3930166 A US 3930166A US 424720 A US424720 A US 424720A US 42472073 A US42472073 A US 42472073A US 3930166 A US3930166 A US 3930166A
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ring
vanes
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Camille Bochard
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Robatel SLPI SA
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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
    • G21F5/06—Details of, or accessories to, the containers
    • G21F5/10—Heat-removal systems, e.g. using circulating fluid or cooling fins

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  • ABSTRACT Package for transporting or enclosing radioactive materials emitting a large amount of heat, having a heat protection device provided between a container metal casing and an external jacket.
  • the device comprises concentric rows of radial metal vanes between which an endothermic insulating material is placed, so that heat emitted by the radioactive material is discharged under optimum conditions, whilst the endothermic material forms an effective heat barrier against external heat.
  • packages of the type in question generally comprise an internal container placed inside an anti-radiation shield (of lead or a similar material).
  • This shield is itself surrounded by an external protective jacket made of metal, which, however, provides an annular space forming a seat for a fire protection device.
  • this protective device must possess very good heat conductivity, so that the heat emitted by the radioactive material contained in the packaging can be discharged and so that any overheating of the shield, made of lead or another material, can be avoided.
  • the protective device should possess very low conductivity so that it can form a screen and effectively prevent any overheating of the shield; however, after the fire the conductivity should remain adequate to discharge the internal heat once more.
  • the aim of the improvements which form the subject of the present invention is more especially to deal with the abovementioned disadvantage and to allow a package to be produced which can contain a radioactive material emitting a large amount of heat, under optimum safety conditions.
  • the fire or heat protection device comprises two concentric rows of metal vanes oriented to extend radially, withcircumfer- ,ential spaces between the vanes of rows being filled with an endothermic insulatingmaterial.
  • the metal vanes consist of lateral flanges or wings, the profiles of which have a U-shaped cross-section, which are made of copper or of another metal of good heat conductivity.
  • the two rows of vanes and the endothermic insulating material which they contain are held between two annular layers of a heat swellable material (of the type of hydrated calcium sulphate) which is a good heat conductor, so that the said vanes are effectively sealed and that heat is transmitted between the various annular layers in use.
  • FIG. 1 is a transverse cross-section of a packaging comprising the improvements according to the invention.
  • FIG. 2 represents a part of FIG. 1 on a larger scale to show the arrangement of the fire protection device.
  • FIG. 3 is a similar view to FIG. 2, but corresponds to an alternative embodiment.
  • the packaging represented in FIG. 1 comprises, in the customary manner, an internal container 1 which has a circular transverse cross-section and is embedded inside a shield or screen 2 made of lead or of another material, which is itself cylindrical in shape.
  • the shield 2 is surrounded by an external protective jacket 3 made of steel or of another resistant metal; the said jacket 3 provides, between its internal wall and the shield 2, an annular space forming a seat fora fire protection device shown schematically at 4.
  • this heat or fire protection device 4 comprises afirst external row or ring of profiled sections 5 which have a U-shaped protile in transverse cross-section; these profiled sections 5, for example made of copper, extend over the entire height of the package and are joined one to another by welding points 5'.
  • the lateral flanges or wings of each profiled section 5, which is held in contact with lateral flanges or wings of adjacent profiled section 5, thus define vanes which are oriented radially toward the inside of the container; the transverse web or bridge of the profiled section which is perforated at intervals at 5a, being turned toward the jacket 3.
  • the protective device also comprises a second internal row or ring of vanes consisting of angle-profiles 6 preferably made of copper, and joined to one another at 6.
  • the angleprofiles 6 are oriented in such a way that one of their wings is placed radially inside a profiled section 5, the two rings being wedged together by means of grooved plates or rods 7 made of wood or of another material which possesses a high coefficient of heat insulation.
  • the spaces provided between the vanes of the two rings 5 and 6 are filled with a mass 8 of a material which is of endothermic nature and can absorb a large amount of heat when subjected to an abrupt rise in temperature.
  • the tworings are sealed in place by means of internal and external annular layers 9 of a material which provides good heat contact.
  • the mass 8 can be produced in accordance with one or other of the two French Pat. Nos. 1,438,241 and 69 27,633.
  • the following composition (by volume) can be used to form the sealing layers 9:
  • the heat emitted by the radioactive material held in the internal container 1 is transmitted to the shield 2 and passes through the internal annular layer 9.
  • the ring formed by the angleprofiles 6 is thus heated to a high temperature; the heat cannot be discharged radially to the outside as a result ofthe heat barrier formed by the wedges or rods 7, so that the heat must pass through each mass 8 to reach the lateral wings of the profiled sections which discharge into the atmosphere through the external annular layer 9 and the metal jacket 2.
  • the heattransmission between the internal ring and the external ring is achieved under excellent conditions as a result of the low circumferential thickness of each of the masses 8 and of the large exchange surface thereby created.
  • the volume of the endothermicinsulating material can be made greater by increasing the radial length of the vanes of the two rings of the fire protection device, and this simultaneously improves the heat insulation of the packaging and the heat discharge characteristics as a result of the increase in the exchange surface,
  • P16. 3 illustrates another embodiment of the invention according to which the shield 2 is lined with a protective neutron screen 10.
  • the angleprofiles 6 comprise a very long radial wing so as to define a space for a suitable material.
  • Use can especially be made of a composition of the following type (the percentages here being given by weight):
  • the screen 10 can consist of a row of bundles formed by polyethylene filaments of small diameter, oriented parallel to each other and coated, for example, by immersion, with a boron-containing binder which, after drying, seals them into the spaces provided between the angle-profiles 6.
  • the screen can have the following composition (by weight):
  • the screen 10 does not in any way disturb the discharge of heat emitted by the radioactive material, since the angle-profiles 6 provide excellent heat conductivity; the heat is dissipated in the same way as in FIG. 2, through the external ring of the profiled sections 5, the layer 9 and the jacket 3.
  • Packaging for enclosing and transporting radioactive material of the type including a material container surrounded by an anti-radiation shield located within a protective metal jacket whose inner wall is spaced from the outer wall of the shield to leave an annular space between said walls for housing an improved protective device operative to insulate the container against heat generated externally of the packaging, the improvement comprising:
  • first and second metal rings concentrically disposed in said annular space and spaced from each other, the first ring being disposed in heat conductive relationship with said jacket and the second ring being disposed in heat conductive relationship with said shield:
  • one of the rings comprises an annular series of mutually attached U-shaped sections each having two legs joined by a web, and the legs of the adjacent sections being radially disposed to form vanes.
  • the rings comprises an annular series of mutually attached angle sections, each having a radially disposed leg forming a vane and an annularly disposed leg form ing a part of the ring.
  • said insulating material comprises a plate having one side lying against a ring and having an opposite side grooved to receive a vane, said plates wedging the alternating vanes together in accurately maintained relationship.
  • sealing material includes hydrated calcium sulphate.
  • sealing material comprises, by volume, substantially:
  • vanes of the second ring are radially longer than the vanes of the first ring, leaving a zone between the rings wherein the vanes are not alternately opposed, and said zone being filled with neutron absorbing material packed between the vanes of the second ring to form a neutron screen.
  • said neutron absorbing material comprises series of bundles each formed of polyethylene filaments coated with a boron-containing binder; the binder joining the bundles to one-another and sealing them between the vanes.
  • the first ring comprises an annular series of attached U-shaped sections, each having two legs joined by a web and the legs of adjacent sections being radially inwardly disposed to form vanes; and wherein the second ring comprises an annular series of attached angle sections, each having a radially disposed leg forming a vane and an annular disposed leg forming a part of the second ring; and the free ends of the vanes being spaced from the opposed ring by insulating material, whereby to prevent heat conductive contact between the vanes and the opposing rings.
  • Packaging according to claim 12, wherein said insulating material comprises plates wedged between the vanes and the opposing rings and grooved to receive the ends of the vanes.
  • vanes of the second ring are radially longer than the vanes of the first ring, leaving a zone between the rings wherein the vanes are not alternately opposed, and said zone being filled with neutron absorbing material packed between the vanes of the second ring to form a neutron screen.

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  • Physics & Mathematics (AREA)
  • Engineering & Computer Science (AREA)
  • General Engineering & Computer Science (AREA)
  • High Energy & Nuclear Physics (AREA)
  • Packages (AREA)
  • Building Environments (AREA)

Abstract

Package for transporting or enclosing radioactive materials emitting a large amount of heat, having a heat protection device provided between a container metal casing and an external jacket. The device comprises concentric rows of radial metal vanes between which an endothermic insulating material is placed, so that heat emitted by the radioactive material is discharged under optimum conditions, whilst the endothermic material forms an effective heat barrier against external heat.

Description

United Stat Bochard PACKAGE FOR TRANSPORTING OR ENCLOSING RADIOACTIVE MATERIALS Camille Bochard, Lyon, France Assignee: Robatel S.L.P.I., Genas, France Filed: Dec. 14, 1973 Appl. No.: 424,720
Inventor:
US. Cl 250/506; 250/515 Int. Cl. G2lf 3/00; G2lf 5/00 Field of Search 250/428, 429,506, 507,
References Cited UNITED STATES PATENTS 3/1969 Nash et al 250/506 3,466,662 9/1969 Blum 250/506 51 Dec. 30, 1975 3,727,060 4/1973 Blum 250/506 Primary ExaminerArchie R. Borchelt Attorney, Agent, or FirmDowell and Dowell [57] ABSTRACT Package for transporting or enclosing radioactive materials emitting a large amount of heat, having a heat protection device provided between a container metal casing and an external jacket. The device comprises concentric rows of radial metal vanes between which an endothermic insulating material is placed, so that heat emitted by the radioactive material is discharged under optimum conditions, whilst the endothermic material forms an effective heat barrier against external heat.
16 Claims, 3 Drawing Figures PACKAGE FOR TRANSPORTING OR ENCLOSING RADIOACTIVE MATERIALS The present invention relates to improvements made to packaging intended to enclose and/or transport radioactive materials safely.
It is known that packages of the type in question generally comprise an internal container placed inside an anti-radiation shield (of lead or a similar material). This shield is itself surrounded by an external protective jacket made of metal, which, however, provides an annular space forming a seat for a fire protection device.
Experience has shown that this fire protection device must possess certain characteristics, some of which appear to be contradictory:
Firstly, under normal conditions of use, this protective device must possess very good heat conductivity, so that the heat emitted by the radioactive material contained in the packaging can be discharged and so that any overheating of the shield, made of lead or another material, can be avoided.
On the other hand, it is vital that, should there be strong source of external heat, such as a fire in the vicinity of the package, the protective device should possess very low conductivity so that it can form a screen and effectively prevent any overheating of the shield; however, after the fire the conductivity should remain adequate to discharge the internal heat once more.
In order to fulfil these two conditions, it has been proposed to produce the fire protection device by filling the annular space provided between the shield and the jacket with a mass of an insulating product of endothermic nature, consisting either of calcium sulphate (CaSO .%H O) as described in French Pat. No. 1,438,241 of 21 Oct. 1964, or of a mixture formed by a suspension of aluminium trihydrate (AI O .3H O) and iron or mild steel powder in water, as claimed in French Pat. No. 69 27,633 (publication No. 2,055,761) of 12, Aug. 1969.
In spite of the advantages offered by such insulating products, a very awkward disadvantage is still encountered. In order to ensure good heat discharge, it is obviously advantageous to reduce the thickness of the insulating mass, whilst in order to ensure that the shield is insulated, the abovementioned mass must, on the other hand, have as large a volume as possible. In practice, a compromise must therefore finally be adopted which does not perfectly satisfy either one or the other of the abovementioned conditions.
The aim of the improvements which form the subject of the present invention is more especially to deal with the abovementioned disadvantage and to allow a package to be produced which can contain a radioactive material emitting a large amount of heat, under optimum safety conditions.
In accordance with the invention, the fire or heat protection device comprises two concentric rows of metal vanes oriented to extend radially, withcircumfer- ,ential spaces between the vanes of rows being filled with an endothermic insulatingmaterial.
It will be understood that such an arrangement makes it possible to give the endothermic insulating material as large a volume as desired; the metal vancs of the two concentric rows ensure effective discharge of the heat emitted by the radioactive material enclosed in the container, whatever the abovementioned volume may be.
' In accordance with a preferred embodiment of the invention, the metal vanes consist of lateral flanges or wings, the profiles of which have a U-shaped cross-section, which are made of copper or of another metal of good heat conductivity. The two rows of vanes and the endothermic insulating material which they contain are held between two annular layers of a heat swellable material (of the type of hydrated calcium sulphate) which is a good heat conductor, so that the said vanes are effectively sealed and that heat is transmitted between the various annular layers in use.
The attached drawing, which is given by way of an example, will allow the invention, the characteristics which it displays and the advantages which it can provide to be better understood:
FIG. 1 is a transverse cross-section of a packaging comprising the improvements according to the invention. I
FIG. 2 represents a part of FIG. 1 on a larger scale to show the arrangement of the fire protection device.
FIG. 3 is a similar view to FIG. 2, but corresponds to an alternative embodiment.
The packaging represented in FIG. 1 comprises, in the customary manner, an internal container 1 which has a circular transverse cross-section and is embedded inside a shield or screen 2 made of lead or of another material, which is itself cylindrical in shape. The shield 2 is surrounded by an external protective jacket 3 made of steel or of another resistant metal; the said jacket 3 provides, between its internal wall and the shield 2, an annular space forming a seat fora fire protection device shown schematically at 4.
As shown more clearly in FIG. 2, this heat or fire protection device 4 comprises afirst external row or ring of profiled sections 5 which have a U-shaped protile in transverse cross-section; these profiled sections 5, for example made of copper, extend over the entire height of the package and are joined one to another by welding points 5'. The lateral flanges or wings of each profiled section 5, which is held in contact with lateral flanges or wings of adjacent profiled section 5, thus define vanes which are oriented radially toward the inside of the container; the transverse web or bridge of the profiled section which is perforated at intervals at 5a, being turned toward the jacket 3. The protective device also comprises a second internal row or ring of vanes consisting of angle-profiles 6 preferably made of copper, and joined to one another at 6. The angleprofiles 6 are oriented in such a way that one of their wings is placed radially inside a profiled section 5, the two rings being wedged together by means of grooved plates or rods 7 made of wood or of another material which possesses a high coefficient of heat insulation. The spaces provided between the vanes of the two rings 5 and 6 are filled with a mass 8 of a material which is of endothermic nature and can absorb a large amount of heat when subjected to an abrupt rise in temperature. The tworings are sealed in place by means of internal and external annular layers 9 of a material which provides good heat contact.
As shown at the beginning of this text, the mass 8 can be produced in accordance with one or other of the two French Pat. Nos. 1,438,241 and 69 27,633. The following composition (by volume) can be used to form the sealing layers 9:
the whole being mixed with 25% of water relative to the volume of dry mixture.
It will be understood that the heat emitted by the radioactive material held in the internal container 1 is transmitted to the shield 2 and passes through the internal annular layer 9. The ring formed by the angleprofiles 6 is thus heated to a high temperature; the heat cannot be discharged radially to the outside as a result ofthe heat barrier formed by the wedges or rods 7, so that the heat must pass through each mass 8 to reach the lateral wings of the profiled sections which discharge into the atmosphere through the external annular layer 9 and the metal jacket 2. It will be understood that the heattransmission between the internal ring and the external ring is achieved under excellent conditions as a result of the low circumferential thickness of each of the masses 8 and of the large exchange surface thereby created.
.vapourise, so that the angle-profiles 6 are only heated to a very moderate degree. Any danger of the shield 2 becoming accidentally overheated is thus avoided; the volume of the endothermicinsulating material can be made greater by increasing the radial length of the vanes of the two rings of the fire protection device, and this simultaneously improves the heat insulation of the packaging and the heat discharge characteristics as a result of the increase in the exchange surface,
During the heating of themasses 8 of endothermic insulating material by a surrounding fire, the steam generated can escape through the perforations 5a of the profiled sections 5 and escape to the outside through orifices provided for this purpose in the jacket 3; theseorifices are normally closed by fusible stoppers 3a;
P16. 3 illustrates another embodiment of the invention according to which the shield 2 is lined with a protective neutron screen 10. In such a case, the angleprofiles 6 comprise a very long radial wing so as to define a space for a suitable material. Use can especially be made of a composition of the following type (the percentages here being given by weight):
polyethylene granules 38% hydrated alumina (Al,O .3H O) l8% colemanite (2CaO.3B O .5H O) 7% cement l4% plaster 7% water As a variant, the screen 10 can consist of a row of bundles formed by polyethylene filaments of small diameter, oriented parallel to each other and coated, for example, by immersion, with a boron-containing binder which, after drying, seals them into the spaces provided between the angle-profiles 6. In practice, the screen can have the following composition (by weight):
polyethylene filaments 75% colemanite 7% cement 6% plaster 5% water 7% This embodiment makes it possible to produce a solid material which is very effective from the point of view of protection against neutrons and is of low density (close to that of water).
It is seen in all cases that the screen 10 does not in any way disturb the discharge of heat emitted by the radioactive material, since the angle-profiles 6 provide excellent heat conductivity; the heat is dissipated in the same way as in FIG. 2, through the external ring of the profiled sections 5, the layer 9 and the jacket 3.
It should furthermore be understood that the preceding description is only given by way of an example and that it in no way limits the scope of the invention, which would not be exceeded by replacing the details of execution which have been described by any other equivalent means. It should in particular be noted that the insulating mouldings 7 can be replaced by a layer of suitable insulating material.
I claim:
1. Packaging for enclosing and transporting radioactive material of the type including a material container surrounded by an anti-radiation shield located within a protective metal jacket whose inner wall is spaced from the outer wall of the shield to leave an annular space between said walls for housing an improved protective device operative to insulate the container against heat generated externally of the packaging, the improvement comprising:
a. first and second metal rings concentrically disposed in said annular space and spaced from each other, the first ring being disposed in heat conductive relationship with said jacket and the second ring being disposed in heat conductive relationship with said shield:
b. radially inwardly extending vanes fixed to the first ring and extending toward the second ring without contacting the latter, and radially outwardly extending vanes fixed to the second ring and extending toward the first ring without contacting the latter, the radially inwardly extending vanes alternating with the radially outwardly extending vanes; and
c. endothermic insulating material filling the spaces between the adjacent vanes.
2. Packaging according to claim 1, wherein one of the rings comprises an annular series of mutually attached U-shaped sections each having two legs joined by a web, and the legs of the adjacent sections being radially disposed to form vanes.
3. Packaging according to claim 1, wherein oncof the rings comprises an annular series of mutually attached angle sections, each having a radially disposed leg forming a vane and an annularly disposed leg form ing a part of the ring.
4. Packaging according to claim 1, wherein the spacing between adjacent vanes is no greater than the radial length of a vane, and wherein insulating material is interposed between the free end of each va'ne and the opposite ring toward which it extends, whereby to prevent heat conductive contact therebetween.
5. Packaging according to claim 4, wherein said insulating material comprises a plate having one side lying against a ring and having an opposite side grooved to receive a vane, said plates wedging the alternating vanes together in accurately maintained relationship.
6. Packaging according to claim 1, wherein said rings are supported within said annular space by heat-conductive sealing material disposed between the first ring and the jacket and between the second ring and the radiation shield.
7. Packaging according to claim 6, wherein the sealing material includes hydrated calcium sulphate.
8. Packaging according to claim 6, wherein the sealing material comprises, by volume, substantially:
Metal Billets 50% Cast Cement 33% Reinforced Plaster [7% the whole being mixed with about 25% of water relative to the volume of the dry mixture.
9. Packaging according to claim 1, wherein the vanes of the second ring are radially longer than the vanes of the first ring, leaving a zone between the rings wherein the vanes are not alternately opposed, and said zone being filled with neutron absorbing material packed between the vanes of the second ring to form a neutron screen.
10. Packaging according to claim 9, wherein said neutron absorbing material comprises series of bundles each formed of polyethylene filaments coated with a boron-containing binder; the binder joining the bundles to one-another and sealing them between the vanes.
11. Packaging according to claim 10, wherein said neutron absorbing material has substantially the following composition by weight:
Polyethylene Filaments Colemanite 7% Cement 6% Plaster 5% Water 7%.
12. Packaging according to claim 1, wherein the first ring comprises an annular series of attached U-shaped sections, each having two legs joined by a web and the legs of adjacent sections being radially inwardly disposed to form vanes; and wherein the second ring comprises an annular series of attached angle sections, each having a radially disposed leg forming a vane and an annular disposed leg forming a part of the second ring; and the free ends of the vanes being spaced from the opposed ring by insulating material, whereby to prevent heat conductive contact between the vanes and the opposing rings.
13. Packaging according to claim 12, wherein said insulating material comprises plates wedged between the vanes and the opposing rings and grooved to receive the ends of the vanes.
14. Packaging according to claim 12, wherein the rings are supported within said annular space by heat conductive sealing material disposed between the first ring and the jacket and between the second ring and the radiation shield.
15. Packaging according to claim 14, wherein the sealing material includes hydrated calcium sulphate.
16. Packaging according to claim 12, wherein the vanes of the second ring are radially longer than the vanes of the first ring, leaving a zone between the rings wherein the vanes are not alternately opposed, and said zone being filled with neutron absorbing material packed between the vanes of the second ring to form a neutron screen.

Claims (16)

1. Packaging for enclosing and transporting radio-active Material of the type including a material container surrounded by an anti-radiation shield located within a protective metal jacket whose inner wall is spaced from the outer wall of the shield to leave an annular space between said walls for housing an improved protective device operative to insulate the container against heat generated externally of the packaging, the improvement comprising: a. first and second metal rings concentrically disposed in said annular space and spaced from each other, the first ring being disposed in heat conductive relationship with said jacket and the second ring being disposed in heat conductive relationship with said shield: b. radially inwardly extending vanes fixed to the first ring and extending toward the second ring without contacting the latter, and radially outwardly extending vanes fixed to the second ring and extending toward the first ring without contacting the latter, the radially inwardly extending vanes alternating with the radially outwardly extending vanes; and c. endothermic insulating material filling the spaces between the adjacent vanes.
2. Packaging according to claim 1, wherein one of the rings comprises an annular series of mutually attached U-shaped sections each having two legs joined by a web, and the legs of the adjacent sections being radially disposed to form vanes.
3. Packaging according to claim 1, wherein one of the rings comprises an annular series of mutually attached angle sections, each having a radially disposed leg forming a vane and an annularly disposed leg forming a part of the ring.
4. Packaging according to claim 1, wherein the spacing between adjacent vanes is no greater than the radial length of a vane, and wherein insulating material is interposed between the free end of each vane and the opposite ring toward which it extends, whereby to prevent heat conductive contact therebetween.
5. Packaging according to claim 4, wherein said insulating material comprises a plate having one side lying against a ring and having an opposite side grooved to receive a vane, said plates wedging the alternating vanes together in accurately maintained relationship.
6. Packaging according to claim 1, wherein said rings are supported within said annular space by heat-conductive sealing material disposed between the first ring and the jacket and between the second ring and the radiation shield.
7. Packaging according to claim 6, wherein the sealing material includes hydrated calcium sulphate.
8. Packaging according to claim 6, wherein the sealing material comprises, by volume, substantially:
9. Packaging according to claim 1, wherein the vanes of the second ring are radially longer than the vanes of the first ring, leaving a zone between the rings wherein the vanes are not alternately opposed, and said zone being filled with neutron absorbing material packed between the vanes of the second ring to form a neutron screen.
10. Packaging according to claim 9, wherein said neutron absorbing material comprises series of bundles each formed of polyethylene filaments coated with a boron-containing binder, the binder joining the bundles to one-another and sealing them between the vanes.
11. Packaging according to claim 10, wherein said neutron absorbing material has substantially the following composition by weight:
12. Packaging according to claim 1, wherein the first ring comprises an annular series of attached U-shaped sections, each having two legs joined by a web and the legs of adjacent sections being radially inwardly disposed to form vanes; and wherein the second ring comprises an annular series of attached angle sections, each haVing a radially disposed leg forming a vane and an annular disposed leg forming a part of the second ring; and the free ends of the vanes being spaced from the opposed ring by insulating material, whereby to prevent heat conductive contact between the vanes and the opposing rings.
13. Packaging according to claim 12, wherein said insulating material comprises plates wedged between the vanes and the opposing rings and grooved to receive the ends of the vanes.
14. Packaging according to claim 12, wherein the rings are supported within said annular space by heat conductive sealing material disposed between the first ring and the jacket and between the second ring and the radiation shield.
15. Packaging according to claim 14, wherein the sealing material includes hydrated calcium sulphate.
16. Packaging according to claim 12, wherein the vanes of the second ring are radially longer than the vanes of the first ring, leaving a zone between the rings wherein the vanes are not alternately opposed, and said zone being filled with neutron absorbing material packed between the vanes of the second ring to form a neutron screen.
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FR2431754A1 (en) * 1978-07-19 1980-02-15 Transnuklear Gmbh Shielded transport container for irradiated fuel elements - has two shielding layers inside external finned casing
FR2471027A1 (en) * 1979-11-17 1981-06-12 Transnuklear Gmbh TRANSPORT AND / OR STORAGE VASE FOR RADIOACTIVE MATERIALS
US4326130A (en) * 1978-10-17 1982-04-20 Stefan Ahner Shielding container with neutron shielding for the transportation and/or storage of spent fuel elements
US4326918A (en) * 1980-03-13 1982-04-27 Electric Power Research Institute, Inc. Storage assembly for spent nuclear fuel
US4328423A (en) * 1980-04-23 1982-05-04 The United States Of America As Represented By The United States Department Of Energy Canister arrangement for storing radioactive waste
EP0143398A2 (en) * 1983-11-29 1985-06-05 Alkem Gmbh Container, in particular for radioactive substances
US4783309A (en) * 1986-06-20 1988-11-08 Deutsche Gesellschaft Fur Wiederaufarbeitung Von Kernbrennstoffen Mbh Double container system for transporting and storing radioactive materials
EP0312902A2 (en) * 1987-10-19 1989-04-26 Westinghouse Electric Corporation Thermal protection shell for radioactive waste containers
US4935943A (en) * 1984-08-30 1990-06-19 The United States Of America As Represented By The United States Department Of Energy Corrosion resistant storage container for radioactive material
WO1995020459A1 (en) * 1994-01-27 1995-08-03 Germania Chemnitz Gmbh Method of creating a welded joint and a transport and storage container for spent nuclear fuel holders produced by the said method
EP0757361A1 (en) * 1995-08-04 1997-02-05 Kabushiki Kaisha Kobe Seiko Sho Transport/storage cask for a radioactive material
US6389093B1 (en) * 1999-06-19 2002-05-14 Gnb Gesellschaft Fur Nuklear-Behalter Mbh Storage/transport container for spent nuclear-fuel elements
EP1355320A1 (en) * 2001-01-25 2003-10-22 Mitsubishi Heavy Industries, Ltd. Cask and production method for cask
US20040125906A1 (en) * 2002-11-09 2004-07-01 Gnb Gesellschaft Fur Nuklear-Behalter Mbh Container for heat-generating radioactive elements
US20040253397A1 (en) * 1995-09-07 2004-12-16 Hayes Claude Q.C. Heat absorbing temperature control devices that include hydroxide
US20090059531A1 (en) * 2007-08-31 2009-03-05 Hayes & Associates Endotherm Systems and Methods Utilizing Carbohydrate In Non-Oxidizing Environment
US20090114856A1 (en) * 2007-10-10 2009-05-07 Kabushiki Kaisha Kobe Seiko Sho (Kobe Steel Ltd.) Transport/storage cask for radioactive material
US20100270001A1 (en) * 2008-08-05 2010-10-28 Parrella Michael J System and method of maximizing grout heat conductibility and increasing caustic resistance
US20130206361A1 (en) * 2010-06-02 2013-08-15 Tn International Packaging for transport and/or storage of radioactive materials, which include improved means of thermal conduction
WO2019184928A1 (en) * 2018-03-29 2019-10-03 何满潮 Nuclide-migration-prevention barrier for underground neutron energy power station and construction method therefor
US10692618B2 (en) 2018-06-04 2020-06-23 Deep Isolation, Inc. Hazardous material canister
US10878972B2 (en) 2019-02-21 2020-12-29 Deep Isolation, Inc. Hazardous material repository systems and methods
US10943706B2 (en) 2019-02-21 2021-03-09 Deep Isolation, Inc. Hazardous material canister systems and methods
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US4326130A (en) * 1978-10-17 1982-04-20 Stefan Ahner Shielding container with neutron shielding for the transportation and/or storage of spent fuel elements
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EP0143398A3 (en) * 1983-11-29 1985-07-17 Alkem Gmbh Container, in particular for radioactive substances
US4935943A (en) * 1984-08-30 1990-06-19 The United States Of America As Represented By The United States Department Of Energy Corrosion resistant storage container for radioactive material
US4783309A (en) * 1986-06-20 1988-11-08 Deutsche Gesellschaft Fur Wiederaufarbeitung Von Kernbrennstoffen Mbh Double container system for transporting and storing radioactive materials
EP0312902A3 (en) * 1987-10-19 1990-01-10 Westinghouse Electric Corporation Thermal protection shell for radioactive waste containers
EP0312902A2 (en) * 1987-10-19 1989-04-26 Westinghouse Electric Corporation Thermal protection shell for radioactive waste containers
WO1995020459A1 (en) * 1994-01-27 1995-08-03 Germania Chemnitz Gmbh Method of creating a welded joint and a transport and storage container for spent nuclear fuel holders produced by the said method
US6187395B1 (en) * 1994-01-27 2001-02-13 Gnb-Gesellschaft Fur Nuklear-Behalter Mbh Process for the production of a weld joint and conveying and storage containers produced according to this process for burned out nuclear fuel cartridges
EP0757361A1 (en) * 1995-08-04 1997-02-05 Kabushiki Kaisha Kobe Seiko Sho Transport/storage cask for a radioactive material
US5641970A (en) * 1995-08-04 1997-06-24 Kabushiki Kaisha Kobe Seiko Sho Transport/storage cask for a radioactive material
US20040253397A1 (en) * 1995-09-07 2004-12-16 Hayes Claude Q.C. Heat absorbing temperature control devices that include hydroxide
US7566484B2 (en) 1995-09-07 2009-07-28 Hayes And Associates Heat absorbing temperature control devices that include hydroxide
US6389093B1 (en) * 1999-06-19 2002-05-14 Gnb Gesellschaft Fur Nuklear-Behalter Mbh Storage/transport container for spent nuclear-fuel elements
EP1355320A1 (en) * 2001-01-25 2003-10-22 Mitsubishi Heavy Industries, Ltd. Cask and production method for cask
US20040062338A1 (en) * 2001-01-25 2004-04-01 Katsunari Ohsono Cask and production method for cask
US6839395B2 (en) * 2001-01-25 2005-01-04 Mitsubishi Heavy Industries, Ltd. Cask and production method for cask
US20050117688A1 (en) * 2001-01-25 2005-06-02 Mitsubishi Heavy Industries Ltd. Cask and method of manufacturing the cask
US7194060B2 (en) * 2001-01-25 2007-03-20 Mitsubishi Heavy Industries, Ltd. Cask and method of manufacturing the cask
EP1355320A4 (en) * 2001-01-25 2010-01-06 Mitsubishi Heavy Ind Ltd Cask and production method for cask
US20040125906A1 (en) * 2002-11-09 2004-07-01 Gnb Gesellschaft Fur Nuklear-Behalter Mbh Container for heat-generating radioactive elements
US20090059531A1 (en) * 2007-08-31 2009-03-05 Hayes & Associates Endotherm Systems and Methods Utilizing Carbohydrate In Non-Oxidizing Environment
US9546312B2 (en) 2007-08-31 2017-01-17 Hayes & Associates Endotherm systems and methods utilizing carbohydrate in non-oxidizing environment
EP2048671A3 (en) * 2007-10-10 2011-03-16 Kabushiki Kaisha Kobe Seiko Sho (Kobe Steel, Ltd.) Transport/storage cask for radioactive material
US7973298B2 (en) 2007-10-10 2011-07-05 Kobe Steel, Ltd. Transport/storage cask for radioactive material
US20090114856A1 (en) * 2007-10-10 2009-05-07 Kabushiki Kaisha Kobe Seiko Sho (Kobe Steel Ltd.) Transport/storage cask for radioactive material
US20100270001A1 (en) * 2008-08-05 2010-10-28 Parrella Michael J System and method of maximizing grout heat conductibility and increasing caustic resistance
US20130206361A1 (en) * 2010-06-02 2013-08-15 Tn International Packaging for transport and/or storage of radioactive materials, which include improved means of thermal conduction
WO2019184928A1 (en) * 2018-03-29 2019-10-03 何满潮 Nuclide-migration-prevention barrier for underground neutron energy power station and construction method therefor
US10692618B2 (en) 2018-06-04 2020-06-23 Deep Isolation, Inc. Hazardous material canister
US10878972B2 (en) 2019-02-21 2020-12-29 Deep Isolation, Inc. Hazardous material repository systems and methods
US10943706B2 (en) 2019-02-21 2021-03-09 Deep Isolation, Inc. Hazardous material canister systems and methods
US11289230B2 (en) 2019-02-21 2022-03-29 Deep Isolation, Inc. Hazardous material canister systems and methods
US11488736B2 (en) 2019-02-21 2022-11-01 Deep Isolation, Inc. Hazardous material repository systems and methods
US11842822B2 (en) 2019-02-21 2023-12-12 Deep Isolation, Inc. Hazardous material canister systems and methods
WO2021204265A1 (en) * 2020-04-09 2021-10-14 上海核工程研究设计院有限公司 Nuclear fuel transport container

Also Published As

Publication number Publication date
GB1403338A (en) 1975-08-28
DE2358979A1 (en) 1974-05-30
FR2208165A1 (en) 1974-06-21
FR2208165B1 (en) 1975-09-12
DE2358979C2 (en) 1984-08-02
JPS5727440B2 (en) 1982-06-10
JPS4995099A (en) 1974-09-10

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