US3845315A - Packaging for the transportation of radioactive materials - Google Patents
Packaging for the transportation of radioactive materials Download PDFInfo
- Publication number
- US3845315A US3845315A US00198556A US19855671A US3845315A US 3845315 A US3845315 A US 3845315A US 00198556 A US00198556 A US 00198556A US 19855671 A US19855671 A US 19855671A US 3845315 A US3845315 A US 3845315A
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- United States
- Prior art keywords
- pressure vessel
- packaging
- gamma ray
- shield
- packaging according
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Classifications
-
- G—PHYSICS
- G21—NUCLEAR PHYSICS; NUCLEAR ENGINEERING
- G21F—PROTECTION AGAINST X-RADIATION, GAMMA RADIATION, CORPUSCULAR RADIATION OR PARTICLE BOMBARDMENT; TREATING RADIOACTIVELY CONTAMINATED MATERIAL; DECONTAMINATION ARRANGEMENTS THEREFOR
- 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
-
- 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
- G21F5/008—Containers for fuel elements
- G21F5/012—Fuel element racks in the containers
Definitions
- the packaging is comprised from easily demountable and replaceable components, including a fluid-tight capsule for containing the radioactive materials, a liquid or gaseous coolant, a gamma ray shield and an outer pressure vessel.
- the latter has cooling elements on its lateral surface and contains a fluid capable of ensuring neutronic protection and evacuation of heat.
- the capsule and gamma ray shield are immersed in the fluid.
- the dimensions of the various components are such that the thickness of the fluid layer between the gamma ray shield and the outer pressure vessel provides adequate neutronic protection. Spacers maintain the components in position.
- a compressible material may be included in compartments between the outer container and the gamma ray shield.
- PAIENTEDnm 29 I974 SERIES n5 2 r. fur 7mm
- the invention relates to packaging used for the shipping of radioactive materials, in particular of irradiated fuel elements requiring shielding against gamma rays and neutrons.
- a shield against gamma rays independent of the inner container or forming part of the latter and placed around its lateral wall, means for shielding against gamma rays being also provided at the levels of the cover and of the bottom of the inner container, and
- an outer container or pressure vessel of high resistance to physical stresses, provided with cooling elements such as fins on it lateral surface and containing water (or another fluid able to ensure neutron shielding and heat transfers) in which the capsule and its surrounding gamma shields are immersed,
- the respective dimensions of these various components of the packaging being such that the thickness of the layer of water comprised between the gamma shield and the pressure vessel is sufficient to ensure the neutron shielding, spacing means being provided to maintain the said components ofthe packaging in predetermined respective positions.
- the abovesaid packaging comprises several inner containers or capsules.
- each of the latter is provided with an individual leak tight lid which is not shielded.
- the capsules are connected at their extremity by welding to a common fluid tight flange cooperating with a flanged cover.
- the said capsules are connected at their lower end by a structure similar to that which connects them at the level of their upper end, this structure cooperating with a common botton, possibly removable.
- the removable common cover and bottom of the abovesaid capsules have a hollow struc ture reinforced by ribs, the said covers and bottom comprising a peripheral flange which is applied, with the interposition of a gasket, against the peripheral flange formed by the plate which connects the capsules.
- the flange of the cover and that of thebottom when the latter is removable, comprises a rim parallel to the axis of the capsules and forming respectively with the cover and the wall of these capsules a peripheral cavity adapted to hold water.
- the invention consists, apart from the abovesaid features, of certain other features which are used preferably, at the same time, and which will be more explicitly considered below.
- FIG. 1 shows in axial cross section one embodiment of a packaging according to the invention
- FIG. 2 is a partial section along the line IIII, of FIG.
- FIG. 3 shows, in radial section, a portion of a second embodiment according to the invention
- FIGS. 4 and 5 show respectively in partial axial section and in radial section, two further embodiments of a packaging according to the invention
- FIGS. 6 and 7 are views in partial axial section showing details ofthe abovesaid packaging corresponding to other embodiments, FIG. 8 being a section along the line VIII-VIII of FIG. 7;
- FIG. 9 shows in partial axial section another embodiment of a packaging according to the invention.
- FIG. 10 is a partial radial section along the line X -X of FIG. 9;
- FIG. 1 shows in partial section, a variation of the structure shown in FIG. 10;
- FIG. I2 lastly, shows in partial axial section, a portion of the packaging of FIG. 9 arranged according to a further preferred embodiment.
- radioactive materials which it is proposed to transport by means of packaging according to the invention are fuel elements irradiated in nuclear plants and having generally an elongated prismatic shape. These elements are withdrawn normally from the reactor at very spaced intervals in batches of about fifty and must then, as soon as possible, be shipped to a reprocessing plant in order to recover certain of their highly valuable constituents.
- At least one leaktight inner container or capsule l which is filled with gas or coolant medium. It is immersed in water contained inside an outer container or pressure vessel 2 which comprises means for heat dissipation 3 outside its lateral surface and, in the case of rather small packaging, thermal insulation 4 at its extremities. Of course, it is possible to provide such an insulation even in the case of larger packaging.
- the abovesaid coolant medium may be a gas, for example air, argon or helium or a liquid, for example water.
- a shield 5, for protection against gamma rays is placed around the lateral wall of the capsule l, and protective means against gamma rays, that is to say shields 6 and 7, of constitution generally similar to that of the shield 5, are placed next to the bottom and the lid of the capsule l.
- the shield 5 can be either independent of the capsule I, or form part of the latter. In the description which follows, these two embodiments are described and their advantages mentioned.
- the respective dimensions of the different components of the packaging are selected so that the thickness of the water layer comprised between the shield 5 and the outer container or pressure vessel 2 is sufficient to ensure neutron shielding.
- spacing means 8 are provided to maintain the different components of the packaging in the predetermined suitable positions.
- spacers may be connected to the shield 5, to the pressure vessel 2, or constitute an independent structure such as will be seen below.
- the shield S is independent of the capsule I.
- This capsule is made generally of stainless steel and the shield 5, which is in the form of a sleeve, is constituted of a core 9 of heavy metal such as lead and uranium surrounded by a sheath I0 of stainless steel.
- the shield 6 forms directly the bottom of the capsule I (it comprises a core 9 of lead or uranium), whilst the shield 7 forms a cover with a core 9 sheathed with stainless steel which. by means of a flange II, is fastened to the flange 13 of the capsule I by means such as bolts 12.
- a gasket 14 which is made, for example, of silicon rubber. It is advantageous to shape the flange 13 so that it comprises an annular shield 15 of similar constitution to that of the shields 6 and 7, which constitution is apparent from the FIG. I. This annular shielding protects in particular the gasket I4.
- the capsule I and the shield 5 are rigidly fixed to one another, by means such as bolt 13a, spacers 16 being provided between the capsule l and the shield 5. for example at the places indicated in the drawing, to enable water, which fills the pressure vessel 2, to circulate by convection between the shield 5 and the fluid tight capsule 1.
- the shield 5 is held in place by the abovesaid spacing means 8 which can be constituted by ribs oriented parallel to the axis of the pressure vessel as seen in the FIG. I.
- all the spacing means are perforated, as shown in FIG. 1, to facilitate water convection.
- the edge of the spacing ribs which are in contact with the capsule I or with the shield 5 and which are thus most exposed to wear are constituted, preferably, of stainless steel.
- the inner wall of the pressure vessel which can, if necessary, be made of carbon steel, is protected against corrosion by stainless steel plating, painting, chemical nickel plating, or any other similar means.
- spacers 8 act as shock absorbers in case of a crash.
- This structure is a kind of basket constructed of ribs 8a parallel to the axis of the packaging and perpendicular rings 8b, said ribs advantageously comprising holes SC for the passage of the water.
- the rings 8b can be smaller in width than the ribs 80. They can also be constituted as shown in FIG. 5.
- the pressure vessel 2 itself is constituted generally by two flanged elements, namely a sleeve 20 on which is fixed permanently, generally by welding, a convex bottom 2b of which the shape is clear from the Figure, and a convex cover 24: of which the shape also is evident from the Figure, which are fastened together, generally by bolts 120.
- a gasket I7 is inserted between the flanges 2d and 2e.
- the insulation 4 which has been considered above and which covers in the case of packagings of small size and, ifdesired, also in packagings oflarge size, the convex bottom and cover 212 and 2c, --it also protects preferably the flanges 2d and 2e--, may be constituted for example of an expanded material 4a covered with a heat-proof coating 4b.
- This insulating coating plays also a damping role in the ease of a fall, in the same manner as the spacing elements 8.
- the cooling elements 3, which have been considered above and which line the outer surface of the sleeve 2a, are preferably constituted by fins of the type of those which form the subject of applicants copending US. Pat. Application Ser. No. 63,529, filed 13 Aug. I970, now allowed.
- a layer 18 of the material of the plaster or cement type with a thickness of only a few centimeters and of which the role is to increase the protection in the case of fire by its cooling action.
- means may be provided such as base plates 19a for example on the portion 26, trunnions 19b for tilting on the part 20, and positioning rim 20 on the part 212.
- the invention gives a solution for this problem by providing between the pressure vessel and the shield for example attached to the spacing structure as shown in FIGS. 7 and 8 open compartments C containing bladders or a compressible expanded material C, such as rubber or plastic foam, the volume of previous expanded material being sufficient to avoid simultaneously neutron beaming and the risk of pressure build up, as the pressure vessel can be filled up with the neutron absorbing liquid (water) and the thermal expansion of said liquid balanced by the compression of the expanded material.
- the volume of the compartments C represents about l percent of the available volume in the pressure vessel.
- the compartments C are distributed so as to reduce local neutron beaming. They can be in the form of tubes parallel to the axis of the packaging and borne by elements 8b as shown.
- a valve 24 To limit the pressure in the case of unusually prolonged fire, there may be provided a valve 24 and, to enable the elimination of the hydrogen formed by radi olysis, a permeable plug" 25 constituted, for example, by a sheet of palladium, may be used.
- the capsule l comprise a filling valve 29 which this time is advantageously provided with a dip tube 30 for level control,
- a permeable plug 33 permeable to hydrogen but tight to gases and radioactive vapors.
- valves or connections not shown enabling the draining and drying of the capsule while in the loading pool.
- FIG. 2 have been shown the partitions 35 used inside the capsule l for spacing the fuel elements 36. Certain constituents of these partitions which are usually made of stainless steel have another composition in order to be an efficient neutronic poison able to prevent criticality.
- the capsule I is fonned by the part ofthe sheath 10 of stainless steel ofthe shield 5 which is directed toward the inside of the packaging.
- the capsule l and the shield 5 form a top-opened container of which the Iateral wall and bottom are made of heavy metal sheathed with stainless steel.
- the packaging according to this embodiment has the same characteristics as that according to the embodiment of FIG. 1. There is no need to detail the common characteristics, which, to the extend that they are shown in FIG. 3, are designated by corresponding ref erence numerals.
- the packaging according to the invention comprises several capsules 1 instead of a single one.
- the means of protection 6 provided at the level of the bottom of the capsules 1 are this time constituted by a cover of constitution similar to that of the shield 5.
- the shielding means 7 are constituted by a cover of identical shape to the cover of the bottom but pierced with four holes of which the shape is apparent from the Figure and in which are fitted the upper ends of the capsules I.
- plugs 70 of constitution similar to that of the shielding 5, bolted onto the said capsules; leaktightness s ensured by a gasket 14, for example of silicon rubber.
- a plate K for example of steel, is provided to tighten the capsules and their plugs 7a, by applying them against the cover 7.
- spacing means such as stops 16 at the places indicated in the drawing.
- FIG. 5 there is also provided a plurality of capsules 1, in this instance seven as is apparent from the Figure, instead of a single one, but this time the said capsules form part of the shielding 5 and it is necessary to withdrawn at the same time the said shielding and the said capsules for the op eration of loading and unloading.
- the heat generated by the fuel elements transported is transmitted by convection of the coolant circulating in contact with the capsule and between the shield and the pressure vessel [or in the channels 37 ofthe embodiment of HO. 3 as well as through the shield 5 in this ease) up to the pressure vessel from which it is dissipated by means of copper fins borne by the latter.
- the heat is transmitted through the shield 5.
- each ofthe capsules l is provided with an individual leak-tight lid such as a blind flange fixed, for example, by means of screws.
- An upper common shield 5b in the form of a cover is provided at the upper part of the packaging.
- the packaging according to the invention offers great flexibility and economy of operation.
- the invention enables safe and rather economical shipment of irradiated fuel elements with defective, cracked or corroded cladding.
- Another advantage resulting from this possibility of only withdrawing the capsule with its contents from the packaging is that the masses handled at the time of loading and unloading operations are much smaller than the total packaging weight, thus enabling the use of overcranes and other lifting apparatus of reduced capacity.
- the removable capsules being loadable in advance or replaceable in a case of abnormal contamination on arrival, the duration of the loading or unloading operations of the packaging are reduced to a considerable extent.
- the amount of coolant, especially contaminated water which is confined within the capsules is reduced to a minimum, and, due also to this structure, the amount of hydrogen formed by radiolysis and by corrosion is reduced in considerable proportions.
- the packaging according to the invention remains leak-tight under normal and accidental conditions of use, and the thickness and shape of the pressure vessel 2 confer on it a special resistance to shock and enable it to withstand high pressures.
- the presence of the insulation at the places not provided with the cooling fins protects the packaging from climatic influences and improves the resistance to fire.
- the position of the neutron shield (water) outside the main gamma shield and its lack of local reduction due to the use of the compartments C results in an economy of weight, the water layer contributing besides, by its high heat capacity. to protection in case of fire.
- the structure of the packaging according to the invention enables the construction also of packaging of great size as well as small packaging, which is important since use of large sized packagings reduces the number of shipments, and use of small sized ones provide the possibility ofcompleting the shipment of one batch without immobilising and oversized packaging. This constitutes considerable progress since, on the one hand packaging containing water already known had necessarily to be of rather heavy weight to resist the accidental conditions of fire, and on the other hand there was no possibility hitherto of constructing a dry" packaging of large size.
- the shield 5 comprises an open container 50 and a cover 5! of identical constitutions, these two elements being connected to one another, for example by bolts 5c.
- the capsules l are united at their upper end by welding to a plate 40 comprising holes 400 at the place of fixing each capsule and forming a peripheral flange 40b, which cooperates with a leak-tight common cover 41 provided with a flange 41b, leak-tightness between the flanges 40b and 41b is ensured by means ofa gasket 44 made for example of silicon rubber.
- the cover 41 has a hollow structure such as is seen from FIGS. 9 and I2 and it is reinforced by ribs 43 delimiting voids 42 which extend the capsules.
- the flange 41b is provided with a rim 45 parallel to the axis of the capsules 1 and forming, in cooperation with the cover 4], as seen in FIGS. 9 and I I, a peripheral cavity 46 capable of holding water due to the presence of which the gasket 44 is kept at a sufficiently low temperature.
- a piping shaped to avoid radiation beaming may be provided through the cover 51.
- each ofthe capsules comprises an individual bottom and is held at a suitable distance from neighboring capsules by means of welded spacers not shown, which gives a sufficient rigidity to the assembly and keeps in position the neutronic poison plates diagrammatically represented at P (FIGS. II and 12) and used to prevent criticality.
- the capsules 1 are united at their lower end by a structure similar to that which unites their upper end, that is to say by a plate 47 comprising holes 47a, and a peripheral flange 47b.
- the lower end of the capsules 1 is closed by a common bottom 49 comprising a peripheral flange 4911 which is applied against the flange 47b.
- a gasket 50 constituted for example of the same material as the gasket 44. It is also possible to fix the bottom 49 by welding. In this case, the gasket 50 is eliminated.
- a rim 51 similar to that provided at the level of the cover 41, in order to form a cavity 52 which can be filled with water.
- the fixing of the cover 41 and that of the bottom 49, when it is removable, can be ensured by any suitable means, for example by bolts such as 53 acting on the flanges 40b and 41b and on the flanges 47b and 49/).
- the capsules 1 are filled with a gaseous or liquid coolant.
- a syphon-drain diagrammatically indicated at 54, and a vent not shown, situated at the level of the common lid 41.
- the capsules 1 as well as their shield 5 are immersed in the water filling the pressure vessel 2.
- the container 5a is made to comprise a plurality of conduits 55 which pass through it and of which the shape is such that it prevents radiation beaming.
- the conduit 55 can be bent as seen in FIGS. 10 and 11.
- conduits 55 are arranged in the vicinity of the lower an upper generatrices of the packaging in the horizontal position of transportion.
- the total cross-section of the conduits at lower and upper levels are about the same.
- bosses 56 are provided on the said shield 5 at these levels, these bosses being directed towards the inside of the shield (FIG, 10), or towards the outside (FIG. 11).
- the core 9 of the shield 5 can comprise parts of lead and others of uranium, the latter being then arranged preferably at the level of the corners.
- the conduit 55 will be buried in the lead.
- the cross-section of the capsules 1 is preferably similar to that of the fule elements to be transported; these elements being often right angle prisms with square bases, the cross-section of the cap sules is frequently square, as seen in FIGS. I0 and I1.
- the shield 5 may be made for example in the manner indicated in FIG. 1].
- the package thus constituted comprises filling, draining and safety devices similar to those which have been described above.
- packaging according to this embodiment may include the improvements described with respect to FIGS. 6 to 8.
- the packaging thus constituted has its own advantages, especially:
- Packaging for the shipment and storage of irradiated materials comprising:
- an outer container forming a pressure vessel having a high resistance to physical stresses and having cooling elements on its outer surface.
- a gamma ray shield located in the pressure vessel and spaced inwardly from the inside wall of the pressure vessel to define therebetween a space, a liquid in said space, the thickness ofthe space being large enough such that the liquid therein ensures neutronic protection and evacuation of heat from the gamma ray shield through to the pressure vessel, said gamma ray shield being readily mountable in and removable from said pressure vessel,
- At lease one leak-tight inner container adapted to contain the irridiated material and a fluid coolant therein, said inner container being easily mountable in and removable from the interior of said gamma ray shield,
- spacing means in said space for fixing the position of the gamma ray shield when it is in the pressure vessel and means securely positioning said inner container when located within the gamma ray shield such that the orientation of the pressure vessel, the gamma ray shield and the inner container remains the same regardless of the orientation of the pres sure vessel, whereby the packaging is operable for properly carrying the gamma ray shield and its contents in either a horizontal or a vertical position.
- Packaging according to claim 1 comprising antineutronic poison plates arranged between the inner containers.
- Packaging according to claim 1. Comprising. between the outer container and the gamma ray shield, compartments containing a compressible material.
- Packaging according to claim 1 comprising means ensuring communication between (a) the space inside the shield and surrounding the one or more inner containers and (b) the space outside the gamma ray shield.
- spacing means are constituted by a structure in the form of a removable basket.
- Packaging according to claim 8 comprising an insulating and shock-abosrbing covering for the places without cooling means.
- the pressure vessel is composed of a sleeve on which has been attached a convex bottom and which is closed at the other end by means of a convex cover, by the cooperation of two flanges provided on these two component elements and the interposition of a leak-tight gasket.
- Packaging according to claim 10 and comprising several inner containers, wherein the inner containers are united at least at one of their ends to a common leak-tight flange cooperating with a cover.
- Packaging according to claim 12, wherein the common peripheral flange of the cover comprises a rim parallel to the axis of the inner containers and forming a peripheral cavity adapted to hold water.
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- Physics & Mathematics (AREA)
- Engineering & Computer Science (AREA)
- General Engineering & Computer Science (AREA)
- High Energy & Nuclear Physics (AREA)
- Packages (AREA)
- Structure Of Emergency Protection For Nuclear Reactors (AREA)
- Details Of Rigid Or Semi-Rigid Containers (AREA)
Applications Claiming Priority (2)
Application Number | Priority Date | Filing Date | Title |
---|---|---|---|
FR7041201A FR2113805B1 (sv) | 1970-11-17 | 1970-11-17 | |
FR7103499A FR2124064B2 (sv) | 1970-11-17 | 1971-02-02 |
Publications (1)
Publication Number | Publication Date |
---|---|
US3845315A true US3845315A (en) | 1974-10-29 |
Family
ID=26216054
Family Applications (1)
Application Number | Title | Priority Date | Filing Date |
---|---|---|---|
US00198556A Expired - Lifetime US3845315A (en) | 1970-11-17 | 1971-11-15 | Packaging for the transportation of radioactive materials |
Country Status (6)
Country | Link |
---|---|
US (1) | US3845315A (sv) |
JP (1) | JPS569679B1 (sv) |
DE (1) | DE2157133C3 (sv) |
FR (2) | FR2113805B1 (sv) |
GB (1) | GB1374099A (sv) |
SE (1) | SE401873B (sv) |
Cited By (47)
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US3962587A (en) * | 1974-06-25 | 1976-06-08 | Nuclear Fuel Services, Inc. | Shipping cask for spent nuclear fuel assemblies |
US4004154A (en) * | 1975-03-17 | 1977-01-18 | Combustion Engineering, Inc. | Fissionable mass storage device |
US4024406A (en) * | 1976-02-17 | 1977-05-17 | Combustion Engineering, Inc. | Spent fuel storage improvement |
US4044267A (en) * | 1975-03-17 | 1977-08-23 | Combustion Engineering, Inc. | Fissionable mass storage device |
US4096392A (en) * | 1975-07-11 | 1978-06-20 | Nuclear Services Corporation | Rack for storing spent nuclear fuel elements |
FR2375694A1 (fr) * | 1976-08-25 | 1978-07-21 | Atomic Energy Authority Uk | Dispositif de transport et de stockage d'elements combustibles radio-actifs |
US4115700A (en) * | 1977-04-04 | 1978-09-19 | Combustion Engineering, Inc. | High density fuel storage racks |
DE2743453A1 (de) * | 1977-09-27 | 1979-03-29 | Kraftwerk Union Ag | Brennelementlagerbehaelter |
US4229316A (en) * | 1978-02-03 | 1980-10-21 | Steag Kernenergie Gmbh | Device for the storage or disposal of radioactive wastes |
EP0020948A2 (en) * | 1979-06-21 | 1981-01-07 | The Carborundum Company | Cask for radioactive material, method of manufacturing such a cask, module used thereby and method of shielding neutrons |
US4274007A (en) * | 1979-02-10 | 1981-06-16 | GNS Gesellschaft fur Nuklear-Service mbH | Radiation-shielding transport and storage vessel |
US4288698A (en) * | 1978-12-29 | 1981-09-08 | GNS Gesellschaft fur Nuklear-Service mbH | Transport and storage vessel for radioactive materials |
US4291536A (en) * | 1977-04-22 | 1981-09-29 | Messier S.A. | Apparatus enabling the storage of radioactive wastes and the recovery of the extraneous heat emitted thereby, and a storage element for incorporation in such apparatus |
US4470950A (en) * | 1980-10-31 | 1984-09-11 | National Nuclear Corporation Limited | Storage arrangements for nuclear fuel elements |
US4532104A (en) * | 1981-04-06 | 1985-07-30 | British Nuclear Fuels Limited | Transport and storage flask for nuclear fuel |
US4680159A (en) * | 1984-08-17 | 1987-07-14 | Deutsche Gesellschaft Fur Wiederaufarbeitung Von Kernbrennstoffen Mbh | Storage container assembly for accommodating individual fuel rods of irradiated nuclear reactor fuel elements |
US4803042A (en) * | 1987-11-23 | 1989-02-07 | Westinghouse Electric Corp. | Nuclear reactor core component shipping container |
US4836975A (en) * | 1986-11-13 | 1989-06-06 | Alkem Gmbh | Container, in particular for a radioactive substance |
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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 |
US5442666A (en) * | 1994-03-04 | 1995-08-15 | Westinghouse Electric Corporation | Apparatus for storing control drive rod shafts during chemical decontamination of a reactor |
US5629963A (en) * | 1992-11-19 | 1997-05-13 | Compagnie Generale Des Matieres Nucleaires | Storage tank for a radioactive fissile material solution |
US5651038A (en) * | 1996-02-06 | 1997-07-22 | Sierra Nuclear Corporation | Sealed basket for pressurized water reactor fuel assemblies |
US6203669B1 (en) | 1997-11-14 | 2001-03-20 | Archimedes Technology Group, Inc. | Nuclear waste separator |
US6258216B1 (en) | 1997-11-14 | 2001-07-10 | Archimedes Technology Group, Inc. | Charged particle separator with drift compensation |
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US20050014988A1 (en) * | 2001-01-29 | 2005-01-20 | Hans Georgii | Device for storing heat generating material and a vessel for such device |
US20050117691A1 (en) * | 2002-06-13 | 2005-06-02 | Framatome Anp Gmbh | Method and apparatus for disposing of a fuel assembly channel of a boiling water reactor plant |
US20060043320A1 (en) * | 1996-05-03 | 2006-03-02 | British Nuclear Fuels Plc | Container for nuclear fuel transportation |
US20070003000A1 (en) * | 2002-03-18 | 2007-01-04 | Singh Krishna P | Method and apparatus for maximizing radiation shielding during cask transfer procedures |
US20080076953A1 (en) * | 2006-07-10 | 2008-03-27 | Singh Krishna P | Apparatus, system and method for facilitating transfer of high level radioactive waste to and/or from a pool |
US20090069621A1 (en) * | 2006-10-11 | 2009-03-12 | Singh Krishna P | Method of removing radioactive materials from a submerged state and/or preparing spent nuclear fuel for dry storage |
US20100155626A1 (en) * | 2008-09-25 | 2010-06-24 | Columbiana Hi Tech Llc | Container for transporting and storing uranium hexaflouride |
US20120067761A1 (en) * | 2009-04-14 | 2012-03-22 | Tn International | Packaging device for the transport and/or storage of a radioactive medium |
US8616404B1 (en) * | 2010-06-03 | 2013-12-31 | Savannah River Nuclear Solutions, Llc | Shipping container |
US20140224677A1 (en) * | 2011-06-13 | 2014-08-14 | Ajou University Industry-Academic Cooperation Foundation | Structure for storing radioactive waste |
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US8995604B2 (en) | 2009-11-05 | 2015-03-31 | Holtec International, Inc. | System, method and apparatus for providing additional radiation shielding to high level radioactive materials |
US20150206610A1 (en) * | 2014-01-22 | 2015-07-23 | Nac International, Inc. | Systems and methods for passive cooling during nuclear fuel transfer |
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US10217537B2 (en) * | 2010-08-12 | 2019-02-26 | Holtec International | Container for radioactive waste |
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Families Citing this family (11)
Publication number | Priority date | Publication date | Assignee | Title |
---|---|---|---|---|
ES401582A1 (es) * | 1971-06-11 | 1977-07-01 | Gen Electric | Un recipiente de transporte para material radioactivo. |
DE2915376C2 (de) * | 1979-04-14 | 1984-02-02 | Transnuklear Gmbh, 6450 Hanau | Behälterkombination für den Transport und die Lagerung bestrahlter Brennelemente aus Kernreaktoren |
DE3063611D1 (en) * | 1979-08-20 | 1983-07-07 | Elektrowatt Ing Ag | Container for carrying radioactive materials |
DE7932527U1 (de) * | 1979-11-17 | 1980-04-24 | Transnuklear Gmbh, 6450 Hanau | Transport- und/oder lagerbehaelter fuer radioaktive stoffe |
DE2952168C2 (de) * | 1979-12-22 | 1982-09-02 | Transnuklear Gmbh, 6450 Hanau | Transport- und/oder Lagerbehälter für radioaktive Stoffe |
DE3028424C2 (de) * | 1980-07-26 | 1984-05-30 | Transnuklear Gmbh, 6450 Hanau | Stoßdämpfer |
DE3306940A1 (de) * | 1982-03-05 | 1983-09-15 | British Nuclear Fuels Ltd., Risley, Warrington, Cheshire | Kernbrennstoff-transportbehaelter |
DE8233960U1 (de) * | 1982-12-03 | 1983-06-16 | Deutsche Gesellschaft für Wiederaufarbeitung von Kernbrennstoffen mbH, 3000 Hannover | Transport- und/oder lagerbehaelter fuer waermeproduzierende radioaktive stoffe |
DE3320071A1 (de) * | 1983-06-03 | 1984-12-06 | Siemens AG, 1000 Berlin und 8000 München | Anordnung zum aufnehmen abgebrannter kernreaktor-brennstaebe und verfahren zu ihrer handhabung |
DE19619432A1 (de) * | 1996-05-14 | 1997-11-20 | Gnb Gmbh | Abschirmbehälter aus Metall für den Transport und/oder die Lagerung von neutronenstrahlenden Gegenständen der Kerntechnik |
US20050286674A1 (en) * | 2004-06-29 | 2005-12-29 | The Regents Of The University Of California | Composite-wall radiation-shielded cask and method of assembly |
Citations (2)
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US3111586A (en) * | 1961-08-25 | 1963-11-19 | Baldwin Lima Hamilton Corp | Air-cooled shipping container for nuclear fuel elements |
US3414727A (en) * | 1965-04-26 | 1968-12-03 | Nat Lead Co | Shipping container for radioactive material including safety shield means |
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GB1136251A (en) * | 1965-01-11 | 1968-12-11 | English Electric Co Ltd | Nuclear reactor fuel handling systems |
US3619616A (en) * | 1969-01-24 | 1971-11-09 | Gen Electric | Forced air cooled radioactive materials container |
-
1970
- 1970-11-17 FR FR7041201A patent/FR2113805B1/fr not_active Expired
-
1971
- 1971-02-02 FR FR7103499A patent/FR2124064B2/fr not_active Expired
- 1971-11-15 US US00198556A patent/US3845315A/en not_active Expired - Lifetime
- 1971-11-17 SE SE7114695A patent/SE401873B/sv unknown
- 1971-11-17 DE DE2157133A patent/DE2157133C3/de not_active Expired
- 1971-11-17 JP JP9228971A patent/JPS569679B1/ja active Pending
- 1971-11-17 GB GB5325871A patent/GB1374099A/en not_active Expired
Patent Citations (2)
Publication number | Priority date | Publication date | Assignee | Title |
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US3111586A (en) * | 1961-08-25 | 1963-11-19 | Baldwin Lima Hamilton Corp | Air-cooled shipping container for nuclear fuel elements |
US3414727A (en) * | 1965-04-26 | 1968-12-03 | Nat Lead Co | Shipping container for radioactive material including safety shield means |
Cited By (69)
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US3962587A (en) * | 1974-06-25 | 1976-06-08 | Nuclear Fuel Services, Inc. | Shipping cask for spent nuclear fuel assemblies |
US4004154A (en) * | 1975-03-17 | 1977-01-18 | Combustion Engineering, Inc. | Fissionable mass storage device |
US4044267A (en) * | 1975-03-17 | 1977-08-23 | Combustion Engineering, Inc. | Fissionable mass storage device |
US4096392A (en) * | 1975-07-11 | 1978-06-20 | Nuclear Services Corporation | Rack for storing spent nuclear fuel elements |
US4024406A (en) * | 1976-02-17 | 1977-05-17 | Combustion Engineering, Inc. | Spent fuel storage improvement |
US4152585A (en) * | 1976-08-25 | 1979-05-01 | United Kingdom Atomic Energy Authority | Assembly for the transport of fuel elements |
FR2375694A1 (fr) * | 1976-08-25 | 1978-07-21 | Atomic Energy Authority Uk | Dispositif de transport et de stockage d'elements combustibles radio-actifs |
US4115700A (en) * | 1977-04-04 | 1978-09-19 | Combustion Engineering, Inc. | High density fuel storage racks |
US4291536A (en) * | 1977-04-22 | 1981-09-29 | Messier S.A. | Apparatus enabling the storage of radioactive wastes and the recovery of the extraneous heat emitted thereby, and a storage element for incorporation in such apparatus |
DE2743453A1 (de) * | 1977-09-27 | 1979-03-29 | Kraftwerk Union Ag | Brennelementlagerbehaelter |
US4229316A (en) * | 1978-02-03 | 1980-10-21 | Steag Kernenergie Gmbh | Device for the storage or disposal of radioactive wastes |
US4288698A (en) * | 1978-12-29 | 1981-09-08 | GNS Gesellschaft fur Nuklear-Service mbH | Transport and storage vessel for radioactive materials |
US4274007A (en) * | 1979-02-10 | 1981-06-16 | GNS Gesellschaft fur Nuklear-Service mbH | Radiation-shielding transport and storage vessel |
EP0020948A2 (en) * | 1979-06-21 | 1981-01-07 | The Carborundum Company | Cask for radioactive material, method of manufacturing such a cask, module used thereby and method of shielding neutrons |
EP0020948A3 (en) * | 1979-06-21 | 1981-06-17 | The Carborundum Company | Cask for radioactive material, method of manufacturing such a cask, module used thereby and method of shielding neutrons |
US4470950A (en) * | 1980-10-31 | 1984-09-11 | National Nuclear Corporation Limited | Storage arrangements for nuclear fuel elements |
US4532104A (en) * | 1981-04-06 | 1985-07-30 | British Nuclear Fuels Limited | Transport and storage flask for nuclear fuel |
US4680159A (en) * | 1984-08-17 | 1987-07-14 | Deutsche Gesellschaft Fur Wiederaufarbeitung Von Kernbrennstoffen Mbh | Storage container assembly for accommodating individual fuel rods of irradiated nuclear reactor fuel elements |
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 |
US4836975A (en) * | 1986-11-13 | 1989-06-06 | Alkem Gmbh | Container, in particular for a radioactive substance |
US4803042A (en) * | 1987-11-23 | 1989-02-07 | Westinghouse Electric Corp. | Nuclear reactor core component shipping container |
US4914306A (en) * | 1988-08-11 | 1990-04-03 | Dufrane Kenneth H | Versatile composite radiation shield |
US5629963A (en) * | 1992-11-19 | 1997-05-13 | Compagnie Generale Des Matieres Nucleaires | Storage tank for a radioactive fissile material solution |
US5442666A (en) * | 1994-03-04 | 1995-08-15 | Westinghouse Electric Corporation | Apparatus for storing control drive rod shafts during chemical decontamination of a reactor |
US5651038A (en) * | 1996-02-06 | 1997-07-22 | Sierra Nuclear Corporation | Sealed basket for pressurized water reactor fuel assemblies |
US6825483B2 (en) | 1996-05-03 | 2004-11-30 | British Nuclear Fuels Plc | Container for nuclear fuel transportation |
US20040011971A1 (en) * | 1996-05-03 | 2004-01-22 | British Nuclear Fuels Plc. | Container for nuclear fuel transportation |
US6770897B2 (en) | 1996-05-03 | 2004-08-03 | British Nuclear Fuels Plc | Container for nuclear fuel transportation |
US8049194B2 (en) | 1996-05-03 | 2011-11-01 | Uranium Asset Management Limited | Container for nuclear fuel transportation |
US20060043320A1 (en) * | 1996-05-03 | 2006-03-02 | British Nuclear Fuels Plc | Container for nuclear fuel transportation |
US20110001066A1 (en) * | 1996-05-03 | 2011-01-06 | British Nuclear Fuels Plc, | Container for nuclear fuel transportation |
US6235250B1 (en) | 1997-11-14 | 2001-05-22 | Archimedes Technology Group, Inc. | Nuclear waste separator |
US6258216B1 (en) | 1997-11-14 | 2001-07-10 | Archimedes Technology Group, Inc. | Charged particle separator with drift compensation |
US6203669B1 (en) | 1997-11-14 | 2001-03-20 | Archimedes Technology Group, Inc. | Nuclear waste separator |
US20050014988A1 (en) * | 2001-01-29 | 2005-01-20 | Hans Georgii | Device for storing heat generating material and a vessel for such device |
US6873673B2 (en) * | 2001-01-29 | 2005-03-29 | Oyster International N.V. | Device for storing heat generating material and a vessel for such device |
US20070003000A1 (en) * | 2002-03-18 | 2007-01-04 | Singh Krishna P | Method and apparatus for maximizing radiation shielding during cask transfer procedures |
US7330525B2 (en) * | 2002-03-18 | 2008-02-12 | Holtec International, Inc. | Method and apparatus for maximizing radiation shielding during cask transfer procedures |
US20050117691A1 (en) * | 2002-06-13 | 2005-06-02 | Framatome Anp Gmbh | Method and apparatus for disposing of a fuel assembly channel of a boiling water reactor plant |
US20080076953A1 (en) * | 2006-07-10 | 2008-03-27 | Singh Krishna P | Apparatus, system and method for facilitating transfer of high level radioactive waste to and/or from a pool |
US8277746B2 (en) | 2006-07-10 | 2012-10-02 | Holtec International, Inc. | Apparatus, system and method for facilitating transfer of high level radioactive waste to and/or from a pool |
US7820870B2 (en) | 2006-07-10 | 2010-10-26 | Holtec International, Inc. | Apparatus, system and method for facilitating transfer of high level radioactive waste to and/or from a pool |
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US7994380B2 (en) | 2006-10-11 | 2011-08-09 | Holtec International, Inc. | Apparatus for transporting and/or storing radioactive materials having a jacket adapted to facilitate thermosiphon fluid flow |
US20090198092A1 (en) * | 2006-10-11 | 2009-08-06 | Singh Krishna P | Method and apparatus for transporting and/or storing radioactive materials having a jacket adapted to facilitate thermosiphon fluid flow |
US8415521B2 (en) | 2006-10-11 | 2013-04-09 | Holtec International, Inc. | Apparatus for providing additional radiation shielding to a container holding radioactive materials, and method of using the same to handle and/or process radioactive materials |
US20090069621A1 (en) * | 2006-10-11 | 2009-03-12 | Singh Krishna P | Method of removing radioactive materials from a submerged state and/or preparing spent nuclear fuel for dry storage |
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Also Published As
Publication number | Publication date |
---|---|
FR2113805A1 (sv) | 1972-06-30 |
DE2157133C3 (de) | 1974-09-26 |
SE401873B (sv) | 1978-05-29 |
JPS569679B1 (sv) | 1981-03-03 |
DE2157133B2 (de) | 1974-02-28 |
FR2113805B1 (sv) | 1976-03-19 |
FR2124064B2 (sv) | 1977-01-14 |
GB1374099A (en) | 1974-11-13 |
FR2124064A2 (sv) | 1972-09-22 |
DE2157133A1 (de) | 1972-05-25 |
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