US3754140A - Transport cask for radioactive material - Google Patents
Transport cask for radioactive material Download PDFInfo
- Publication number
- US3754140A US3754140A US00094444A US3754140DA US3754140A US 3754140 A US3754140 A US 3754140A US 00094444 A US00094444 A US 00094444A US 3754140D A US3754140D A US 3754140DA US 3754140 A US3754140 A US 3754140A
- Authority
- US
- United States
- Prior art keywords
- cask
- walls
- cylindrical
- vessel
- honeycomb material
- Prior art date
- Legal status (The legal status is an assumption and is not a legal conclusion. Google has not performed a legal analysis and makes no representation as to the accuracy of the status listed.)
- Expired - Lifetime
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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
- G21F5/08—Shock-absorbers, e.g. impact buffers for containers
Definitions
- the present assembly has been designed for highway transport of radioactive materials, such as solid, liquid or gaseous waste.
- radioactive materials such as solid, liquid or gaseous waste.
- the growing use of nuclear reactors for power purposes necessitates the transport of radioactive waste materials in considerable volume to remote disposal sites. It is essential that the radioactive material be transported within a package designed within the weight limits applicable to highway transport vehicles and capable of safely containing the material in the event of any accident.
- the design of the present cask assembly is such that it alone is capable of withstanding any normal impact load to which the assembly might be subjected during highway transport, the cask being freely carried within an upright cradle on a truck bed. It does not require any fixed anchorage to the truck bed. It includes a separable sealed cask that serves as a containment vessel and an overpack designed to absorb impact forces without rupture of the sealed cask.
- the invention described herein relates to a cask assembly including an inner containment vessel or cask and an outer double-walled vessel or cask overpack.
- the cask comprises a body including radioactive shielding material and a removable lid with a compressible sealing arrangement interposed between the lid and body.
- the cask overpack comprises a doublewalled vessel that completely encloses the cask in an enlarged cylindrical configuration.
- the inner and outer walls are spaced by directionally oriented honeycomb material designed to withstand internal and external forces in compression so as to prevent accidental rupturing of the cask.
- Another object of this invention is to provide such a cask assembly capable of use within the normal weight limits applicable to highway vehicles.
- Another object of this invention is to provide a twopiece cask assembly wherein the radioactive containment vessel can be readily separated from the cask overpack for loading and handling purposes.
- Another object of this invention is to provide such a cask assembly which does not place any reliance upon anchorage to a vehicle for structural integrity or physical protection of the material being transported.
- the present cask is not fixed to the vehicle, and is free to separate from the vehicle should it be overturned.
- the design of the cask is such as to be capable of withstanding impact without external protection of any sort.
- FIG. 1 is a side elevation view of the cask mounted on a transport truck
- FIG. 2 is an enlarged top view of the cask assembly and cradle shown in FIG. 1;
- FIG. 3 is an enlarged vertical sectional view taken through the cask along line 3-3 in FIG. 2;
- FIG. 4 is a sectional view through the cask assembly as seen along line 44 in FIG. 3, taken at a reduced scale;
- FIG. 5 is an enlarged fragmentary sectional view showing the inner cask seal details
- FIG. 6 is an enlarged fragmentary view showing the upper portion of the cradle assembly as seen along line 66 in FIG. 2.
- the drawings illustrate a preferred form of the invention, designed specifically for transporting radioactive materials, such as resins contaminated with radioactive materials for waste disposal purposes.
- the cask assembly has been designed to meet applicable highway standards for safe transport of such materials and to be capable of transporting large quantities of materials within present weight limits.
- the cask assembly comprises an inner cylindrical cask l0 and an outer cask overpack 20, also of cylindrical shape.
- the cask overpack 20 and the cask 10 received therein are held in place on a conventional-flatbed trailer 11 by means of a cradle 12.
- the cradle 12 comprises a rigid circular ring 13 that encircles the outside walls of cask overpack 20 and which is supported on the trailer 11 by four upright standards 14.
- the cask assembly is not rigidly anchored to the flatbed trailer 11 and is capable of falling from its normal location within cradle 12 should the trailer 11 be accidentally upset.
- the cask assembly is designed to be independently capable of withstanding all normal physical impact forces to which it might be subjected.
- Cask 10 serves as a sealed containment vessel for materials received therein. It is in the fonn of a right cylinder with external attachments.
- Cask 10 is preferably constructed in the form of a double-walled lead-filled configuration with inner surfaces of stainless steel and an outer structural steel shell with a thermal shield sandwiched between the steel and lead sections. It basically includes a cylindrical body 15 open at one axial end, and a removable end cover or lid 16 normally held in place by a plurality of bolts 17 spaced about its circular periphery.
- the body 15 and lid 16 of cask 10 are constructed of substantially identical layers of material. Each includes a relatively thick outer shell 21 of carbon steel suitable for structural use. The shell 21 is formed about a core of lead 22 for radioactive shielding purposes.
- a thermal barrier is interposed between the lead at 22 and the outer shell 21 in the form of a continuous layer of asbestos 19.
- the purpose of this layer 19 (FIG. 5) is to prevent melting of the lead or thermal injury to the cask contents if subjected to fire.
- Other suitable materials such as wood, may be substituted to provide a suitable thermal barrier or to meet required specifications for such of such articles.
- the inner shell of body is completed by a relatively thin layer of stainless steel 23.
- a structural layer of steel 24 protects the lead core of lid 16.
- Lid 16 comprises a round recessed plugtype cover sealed by a specially designed resilient seal as discussed below.
- the cask overpack 20 contains substantial amounts of directionally oriented honeycomb type material designed to withstand all anticipated external impact loads to which the assembly might be subjected.
- the cask overpack 20 is a totally enclosed vessel comprising a hollow steel shell containing honeycomb material arranged to present maximum impact resistance to the direction of impact.
- the overpack 20 comprises a cylindrical body and cover 26 of identical construction, which cooperatively receives cask 10. They are constructed of an inner steel shell 27 and an outer steel shell 28. The radially spaced cylindrical walls of shells 27, 28 are separated by a cylindrical wrap of honeycomb material 30 having the cells thereof oriented radially with respect to the upright center axis of the cask assembly.
- the end walls of shells 27, 28 which are axially separated, are spaced by sheets of honeycomb material 31 in the shape of a frustrum of a cone.
- the large base of the frustrum is substantially identical in diameter to the diameter of the end walls of inner shell 27.
- the opposite parallel surface of each sheet 31 is circular and of smaller diameter than such end walls.
- the conical surface 32 about each sheet 31 is at a right angle to a line drawn between the outer corner of the cask overpack (indicated at 33 in FIG. 7) and the design center of gravity of the loaded cask assembly (indicated at 34 in FIG. 7).
- the end surfaces of the cylindrical wrap of honeycomb material 30 which are indicated at 35 in FIG. 3, are formed as a continuation of the surfaces 32.
- the remaining space between the shells 27, 28 is filled by two annular rings 35 of honeycomb material oriented with the cells thereof substantially parallel to the line connecting points 33, 34 in FIG. 7.
- the rings 35 are designed to provide maximum impact absorption within the vessel should it be dropped on the external corners of the cask overpack 20.
- the cover 26 is selectively secured to the body 25 of the overpack 20 by external overlapping flanges 36 which protrude along body 25 and which are selectively secured thereto by a plurality of bolts 37.
- the cask 10 is defined to be removed from the overpack 20 for loading and unloading purposes, while the overpack 20 will normally remain in place within cradle 12 except for repair purposes.
- the lifting of cask 10 is accomplished by three radial steel lugs welded to the upper rim of the outer shell 21.
- the removable lid 16 is similarly provided with three lugs 39 angularly aligned with the respective lugs 38 (FIG. 4).
- the honeycombed material within the overpack cover 26 are suitably relieved at 40 to provide clearance for the reception of lugs 38, 29.
- lifting lugs 41 are provided along the top rim of the overpack cover 26 to facilitate removal of the cover 26.
- the seal provided between lid 16 and body 15 in the cask 10 is shown in detail in FIG. 5. It comprises an annular ring 42 molded of a compressible resin, such as polyurethane, or foam rubber that is engaged by an annular ring 43 of stainless steel fixed to the inner surface of the cask layer 23 and extending toward the open end of the cask body 15.
- the projecting edge of ring 43 is concentric with the ring 42.
- the compression of ring 42 insures a gas-tight seal capable of withstanding considerable deformation of the vessel while maintaining the seal intact.
- the seal can be designed to withstand short time temperatures of an elevated nature without destroying its sealing capability.
- Case 10 can be designed to provide effective radioactive shielding capability within present standards for transport purposes.
- the lead cover 22 and outer shell 21 are both 2 inches thick.
- the contemplated load within cask 10 is mounted within an overpack 20 having a shell spacing of approximately 15 inches at the cylindrical sides and approximately 13 inches at the axial ends.
- the lugs 38 and 39 are each designed so as to be more weak than the structural shell to which they are secured. Thus, any structural failure due to lifting forces applied to the lugs will occur in the lugs and will not result in rupture of the structural components of the cask 10.
- FIG. 3 illustrates the use of the cask assembly for carrying radioactive waste in the form of solid resin in a conventional storage pot 44.
- the pot 44 is fixed within the interior of cask 10 by a lower block of honeycomb 45 and a surrounding cylindrical wrap of honeycomb 46 spaced slightly from the sides of pot 44 by two annular rings of rubber cushion material shown at 47.
- the upper platform of pot 44 is engaged by a sheet of honeycomb 48 on the inner surface of the cask lid 16.
- the cask assembly is not fixed to the trailer 1 1. It sits tightly within cradle 12, being surrounded by the horizontal ring 13. As seen in FIG. 2, the cask assembly is surrounded by a ring 29 of rubber belting or other suitable compressible material wedged between ring 13 and the outer shell 28 of overpack 20.
- the ring 29 is radially compressed and is preferably riveted and glued to the inner surface of ring 13 so as to remain in place when overpack 20 is removed from cradle 12.
- FIG. 6 shows a modification of the cradle support in which compressed rubber blocks are substituted for the full ring 29.
- a wedged block of rubber 48 which fits tightly between ring 13 and the outer shell 28 of the cask overpack 20.
- each block 48 is tapered in thickness and has an original configuration illustrated by dashed lines at 50.
- the blocks 48 or ring 29 attenuate vibration between the trailer 11, cradle 12 and the cask assembly.
- the cask 10 is designed to serve as a shielding container to maintain the containment of radioactivity under all anticipated conditions.
- the cask assembly can be fabricated of all-welded construction except for the heavily bolted lid and cover and is therefore not substantially affected by vibration incident to travel. Because the cask is constructed of metal, it is not disturbed by exposure to water spray.
- the overpack 20 has been designed to accomodate and absorb the forces resulting from impact of the cask assembly due to any foreseeable accident without disrupting the integrity of the inner cask 10.
- the cask assembly can further be utilized to handle other waste materials requiring radioactive shielding during transport.
- the cushioning materials shown within cask are subject to variation in order to conform to the size and shape of the load carried thereby.
- a cask assembly for the transport of radioactive materials while supported on a vehicle bed free of restraining attachment to the vehicle comprising:
- a rigid cylindrical cask having walls containing radioactive shielding material, said cask being formed of an integral body open at one axial end and a complimentary lid removably fixed thereto;
- sealing means operatively interposed between the lid and body of said cask
- a rigid circular cylindrical cask overpack comprisdouble-walled cylindrical vessel totally enclosing said cask including inner walls complimentary to said cask, outer walls spaced from the inner walls, and honeycomb material interposed between the inner and outer walls thereof having cell orientations substantially perpendicular to the respective directions of maximum impact exposure of the walls and corners of the vessel;
- said vessel including a removable lid assembly at one axial end thereof for permitting entry and removal of the cask.
- annular rings of honeycomb material located between the comers of the inner and outer shells at the respective ends thereof, said annular rings each having the cells thereof aligned substantially parallel to the sides of a cone having the designed center of gravity of the loaded cask assembly as its apex and the respective outer shell end wall as its base.
- a cask assembly as set out in claim 1 wherein the double-walled vessel comprises cylindrical inner and outer shells including radially spaced cylindrical walls aligned along a central axis and axially spaced end walls perpendicular to said axis and extending across the respective ends of said cylindrical walls:
- each sheet being in the form of a truncated cone aligned along said central axis and having one circular end thereof corresponding in diameter to the inner end wall abutted thereby, the remaining circular end being of small diameter and abutting the outer end wall;
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- Physics & Mathematics (AREA)
- Engineering & Computer Science (AREA)
- General Engineering & Computer Science (AREA)
- High Energy & Nuclear Physics (AREA)
- Processing Of Solid Wastes (AREA)
Abstract
Description
Claims (5)
Applications Claiming Priority (1)
Application Number | Priority Date | Filing Date | Title |
---|---|---|---|
US9444470A | 1970-12-02 | 1970-12-02 |
Publications (1)
Publication Number | Publication Date |
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US3754140A true US3754140A (en) | 1973-08-21 |
Family
ID=22245239
Family Applications (1)
Application Number | Title | Priority Date | Filing Date |
---|---|---|---|
US00094444A Expired - Lifetime US3754140A (en) | 1970-12-02 | 1970-12-02 | Transport cask for radioactive material |
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US (1) | US3754140A (en) |
Cited By (27)
Publication number | Priority date | Publication date | Assignee | Title |
---|---|---|---|---|
US4175669A (en) * | 1976-07-01 | 1979-11-27 | Greer Norman L | Overpack for nuclear fuel container |
US4232730A (en) * | 1977-05-16 | 1980-11-11 | Reese Stanton L | Radioactive materials transporting container and vehicles |
FR2487565A1 (en) * | 1980-07-26 | 1982-01-29 | Transnuklear Gmbh | SHOCK ABSORBER FOR TRANSPORT CONTAINERS AND / OR STORAGE OF RADIOACTIVE MATERIALS |
EP0049437A1 (en) * | 1980-10-02 | 1982-04-14 | TRANSNUKLEAR GmbH | Container for transport and/or storage of radioactive substances using a shock absorber |
EP0054944A1 (en) * | 1980-12-22 | 1982-06-30 | STEAG Kernenergie GmbH | Storage equipment for radioactive material |
FR2518066A1 (en) * | 1981-12-11 | 1983-06-17 | Caoutchouc Manuf Plastique | Shock protection device for drums contg. radioactive prods. - where cage made in two halves and covered with flexible rubber buffers can be rapidly assembled round drum |
US4395052A (en) * | 1980-04-03 | 1983-07-26 | Proco, Inc. | Uranium slurry hauling system |
US4702391A (en) * | 1984-12-22 | 1987-10-27 | Kernforschungszentrum Karlsruhe Gmbh | Containment with long-time corrosion resistant cover for sealed containers with highly radioactive content |
US4747512A (en) * | 1987-06-19 | 1988-05-31 | Lo Kin K | Transportation packaging for liquids |
US4780269A (en) * | 1985-03-12 | 1988-10-25 | Nutech, Inc. | Horizontal modular dry irradiated fuel storage system |
US4862007A (en) * | 1987-10-19 | 1989-08-29 | Westinghouse Electric Corp. | Thermal protection shell for radioactive waste containers |
US4875200A (en) * | 1988-11-01 | 1989-10-17 | The United States Of America As Represented By The Secretary Of The Army | Illuminating bezel |
US5061858A (en) * | 1987-10-19 | 1991-10-29 | Westinghouse Electric Corp. | Cask assembly for transporting radioactive material of different intensities |
US5394449A (en) * | 1993-10-08 | 1995-02-28 | Pacific Nuclear Systems, Inc. | Impact limiter for spent nuclear fuel transportation cask |
WO1995010839A1 (en) * | 1993-10-08 | 1995-04-20 | Vectra Technologies, Inc. | Impact limiter for spent nuclear fuel transportation cask |
WO2001022430A1 (en) * | 1999-09-18 | 2001-03-29 | British Nuclear Fuels Plc | A protective casing |
EP1187145A1 (en) * | 2000-09-11 | 2002-03-13 | GNB Gesellschaft für Nuklear-Behälter mbH | Shock-absorber for a container |
US20020122523A1 (en) * | 2000-10-20 | 2002-09-05 | Hitachi, Ltd. | Method of treating large scale structural body |
US6812475B1 (en) * | 2004-02-02 | 2004-11-02 | Roger C. P. Huang | Device for storing radioactive material and shipping apparatus for the same |
US20040258191A1 (en) * | 2001-04-27 | 2004-12-23 | Hitachi, Ltd. | Method of handling a structure and equipment of handling the same |
WO2006115991A2 (en) * | 2005-04-22 | 2006-11-02 | Vulcan Lead, Inc. | Shielded containment system and method of operating the same |
EP1721322A1 (en) * | 2004-02-10 | 2006-11-15 | Framatome ANP GmbH | Storage transport system and method for storing and transporting nuclear waste |
US20080073601A1 (en) * | 2006-08-24 | 2008-03-27 | Temus Charles J | Transportation container and assembly |
US20110091003A1 (en) * | 2006-01-25 | 2011-04-21 | Commissariat A L'energie Atomique | Method and device for sealing a canister loaded with irradiated nuclear fuel in a cooling pond |
EP2579263A4 (en) * | 2010-05-25 | 2013-10-23 | Mitsubishi Heavy Ind Ltd | Radioactive substance storage container |
US20190118695A1 (en) * | 2017-10-20 | 2019-04-25 | Lauren R. Isaac | Enclosed transport trailer for hauling an elongated body |
US11676736B2 (en) * | 2017-10-30 | 2023-06-13 | Nac International Inc. | Ventilated metal storage overpack (VMSO) |
Citations (4)
Publication number | Priority date | Publication date | Assignee | Title |
---|---|---|---|---|
US2773459A (en) * | 1950-09-23 | 1956-12-11 | Paul S Sechy | Protective wall for use against radiation and explosive forces |
US3056028A (en) * | 1960-05-03 | 1962-09-25 | James T Mattingly | Neutron shielding structure |
US3229096A (en) * | 1963-04-03 | 1966-01-11 | Nat Lead Co | Shipping container for spent nuclear reactor fuel elements |
US3391280A (en) * | 1964-11-06 | 1968-07-02 | Nat Lead Co | Fire protection shield for radioactive shipping container |
-
1970
- 1970-12-02 US US00094444A patent/US3754140A/en not_active Expired - Lifetime
Patent Citations (4)
Publication number | Priority date | Publication date | Assignee | Title |
---|---|---|---|---|
US2773459A (en) * | 1950-09-23 | 1956-12-11 | Paul S Sechy | Protective wall for use against radiation and explosive forces |
US3056028A (en) * | 1960-05-03 | 1962-09-25 | James T Mattingly | Neutron shielding structure |
US3229096A (en) * | 1963-04-03 | 1966-01-11 | Nat Lead Co | Shipping container for spent nuclear reactor fuel elements |
US3391280A (en) * | 1964-11-06 | 1968-07-02 | Nat Lead Co | Fire protection shield for radioactive shipping container |
Cited By (34)
Publication number | Priority date | Publication date | Assignee | Title |
---|---|---|---|---|
US4175669A (en) * | 1976-07-01 | 1979-11-27 | Greer Norman L | Overpack for nuclear fuel container |
US4232730A (en) * | 1977-05-16 | 1980-11-11 | Reese Stanton L | Radioactive materials transporting container and vehicles |
US4395052A (en) * | 1980-04-03 | 1983-07-26 | Proco, Inc. | Uranium slurry hauling system |
FR2487565A1 (en) * | 1980-07-26 | 1982-01-29 | Transnuklear Gmbh | SHOCK ABSORBER FOR TRANSPORT CONTAINERS AND / OR STORAGE OF RADIOACTIVE MATERIALS |
EP0049437A1 (en) * | 1980-10-02 | 1982-04-14 | TRANSNUKLEAR GmbH | Container for transport and/or storage of radioactive substances using a shock absorber |
US4627956A (en) * | 1980-10-02 | 1986-12-09 | Transnuclear Gmbh | Shock absorbers |
EP0054944A1 (en) * | 1980-12-22 | 1982-06-30 | STEAG Kernenergie GmbH | Storage equipment for radioactive material |
US4488048A (en) * | 1980-12-22 | 1984-12-11 | Steag Kernenergie Gmbh | Container for the storage of radioactive material |
FR2518066A1 (en) * | 1981-12-11 | 1983-06-17 | Caoutchouc Manuf Plastique | Shock protection device for drums contg. radioactive prods. - where cage made in two halves and covered with flexible rubber buffers can be rapidly assembled round drum |
US4702391A (en) * | 1984-12-22 | 1987-10-27 | Kernforschungszentrum Karlsruhe Gmbh | Containment with long-time corrosion resistant cover for sealed containers with highly radioactive content |
US4780269A (en) * | 1985-03-12 | 1988-10-25 | Nutech, Inc. | Horizontal modular dry irradiated fuel storage system |
US4747512A (en) * | 1987-06-19 | 1988-05-31 | Lo Kin K | Transportation packaging for liquids |
US4862007A (en) * | 1987-10-19 | 1989-08-29 | Westinghouse Electric Corp. | Thermal protection shell for radioactive waste containers |
US5061858A (en) * | 1987-10-19 | 1991-10-29 | Westinghouse Electric Corp. | Cask assembly for transporting radioactive material of different intensities |
US4875200A (en) * | 1988-11-01 | 1989-10-17 | The United States Of America As Represented By The Secretary Of The Army | Illuminating bezel |
WO1995010839A1 (en) * | 1993-10-08 | 1995-04-20 | Vectra Technologies, Inc. | Impact limiter for spent nuclear fuel transportation cask |
US5394449A (en) * | 1993-10-08 | 1995-02-28 | Pacific Nuclear Systems, Inc. | Impact limiter for spent nuclear fuel transportation cask |
WO2001022430A1 (en) * | 1999-09-18 | 2001-03-29 | British Nuclear Fuels Plc | A protective casing |
EP1187145A1 (en) * | 2000-09-11 | 2002-03-13 | GNB Gesellschaft für Nuklear-Behälter mbH | Shock-absorber for a container |
US20020122523A1 (en) * | 2000-10-20 | 2002-09-05 | Hitachi, Ltd. | Method of treating large scale structural body |
US20040258191A1 (en) * | 2001-04-27 | 2004-12-23 | Hitachi, Ltd. | Method of handling a structure and equipment of handling the same |
US6812475B1 (en) * | 2004-02-02 | 2004-11-02 | Roger C. P. Huang | Device for storing radioactive material and shipping apparatus for the same |
US20100270482A1 (en) * | 2004-02-10 | 2010-10-28 | Framatome Anp Gmbh | Storage-transport system and method for storing and transporting radioactive waste |
EP1721322A1 (en) * | 2004-02-10 | 2006-11-15 | Framatome ANP GmbH | Storage transport system and method for storing and transporting nuclear waste |
WO2006115991A3 (en) * | 2005-04-22 | 2007-05-24 | Vulcan Lead Inc | Shielded containment system and method of operating the same |
US20080277603A1 (en) * | 2005-04-22 | 2008-11-13 | Yanke Paul H | Shielded Containment System and Method of Operating the Same |
WO2006115991A2 (en) * | 2005-04-22 | 2006-11-02 | Vulcan Lead, Inc. | Shielded containment system and method of operating the same |
US20110091003A1 (en) * | 2006-01-25 | 2011-04-21 | Commissariat A L'energie Atomique | Method and device for sealing a canister loaded with irradiated nuclear fuel in a cooling pond |
US8416910B2 (en) * | 2006-01-25 | 2013-04-09 | Commissariat A L'energie Atomique | Method and device for sealing a canister loaded with irradiated nuclear fuel in a cooling pond |
US20080073601A1 (en) * | 2006-08-24 | 2008-03-27 | Temus Charles J | Transportation container and assembly |
US8003966B2 (en) * | 2006-08-24 | 2011-08-23 | Areva Federal Services Llc | Transportation container and assembly |
EP2579263A4 (en) * | 2010-05-25 | 2013-10-23 | Mitsubishi Heavy Ind Ltd | Radioactive substance storage container |
US20190118695A1 (en) * | 2017-10-20 | 2019-04-25 | Lauren R. Isaac | Enclosed transport trailer for hauling an elongated body |
US11676736B2 (en) * | 2017-10-30 | 2023-06-13 | Nac International Inc. | Ventilated metal storage overpack (VMSO) |
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