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
  • G21F5/14—Devices for handling containers or shipping-casks, e.g. transporting devices loading and unloading, filling of containers
• • 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
• • G—PHYSICS
  • G21—NUCLEAR PHYSICS; NUCLEAR ENGINEERING
  • G21F—PROTECTION AGAINST X-RADIATION, GAMMA RADIATION, CORPUSCULAR RADIATION OR PARTICLE BOMBARDMENT; TREATING RADIOACTIVELY CONTAMINATED MATERIAL; DECONTAMINATION ARRANGEMENTS THEREFOR
  • G21F5/00—Transportable or portable shielded containers
  • G21F5/005—Containers for solid radioactive wastes, e.g. for ultimate disposal

Definitions

• the invention relates to a storage transport system and a method for storing and transporting radioactive waste.
• radioactive waste is generated in particular when generating energy using nuclear power.
• this also includes low and medium-level radioactive waste, for example contaminated equipment.
• Liquid radioactive waste is often poured into a solid mass in a cementing plant, which is poured into barrels, for example.
• these containers in which the radioactive waste is introduced, must meet the requirements for storage in the interim storage facility and in the final storage facility as well as the requirements for necessary transportation, for example between the interim storage facility and the final storage facility.
• very high demands are placed on the containers overall, both with regard to the shielding of the radiation from the radioactive waste contained in the container and with regard to a sufficiently high level of transport safety, for example due to a sufficiently high mechanical stability to prevent the accident during transport Avoid radioactive leakage safely.
• the containers must be designed to be transportable and manageable. These requirements make today's transport and storage containers very complex and correspondingly expensive.
• the invention is based on the object of enabling simplified and less expensive storage and simplified and less expensive transportation, in particular of low and medium-level radioactive waste.
• a storage transport system for the storage and transport of radioactive waste, in which a storage container is provided for receiving the radioactive waste, the storage container being designed such that it merely meets the requirements for storage in a storage facility, Interim storage in particular meets, but not the requirements for transport outside the warehouse, and the storage container is provided for transport outside the warehouse for arrangement in a transport container, which is designed such that the higher transport requirements are met.
• This embodiment is based on the idea of taking into account the different requirements for storage and transport by separating the storage function from the transport function of a container for radioactive waste and dividing it into two containers designed for different requirements.
• a special storage container is provided, which is placed in a suitable transport container for transport. Due to the lower requirements for storage in the interim storage facility, this measure makes the storage container much simpler and, in particular, more cost-effective than is possible with the containers customary today, which are designed both for storage and for transport.
• requirements are placed on the containers with regard to the shielding of the radioactive radiation and with regard to the mechanical stability. Both requirements are usually in the interim storage facility significantly lower, since there is no risk of accidents when storing compared to transport (mechanical stability).
• the interim storage facility itself which is designed as a separate building wing on the site of a nuclear facility, for example, provides a shielding power for the radioactive radiation, whereas the containers come into direct contact with the environment and therefore better shielding must have than in the interim storage facility.
• the containers must be designed in such a way that a permissible maximum radiation dose rate is not exceeded.
• the storage container is expediently designed only for maintaining a higher maximum permissible radiation dose rate in the intermediate storage facility, but not for maintaining a lower maximum permissible radiation dose rate outside the intermediate storage facility. It is only through the arrangement of the storage container in the transport container that the lower maximum permissible radiation dose rate outside the intermediate storage is undershot.
• the storage container is provided for arranging several containers with radioactive waste, in particular for arranging drums. This simplifies the handling of the containers and enables them to be handled together. There is also the possibility, if necessary, of providing additional measures for shielding and for increasing the mechanical stability.
• the containers stored in the storage container are preferably cast in the storage container.
• the storage container is provided without the use of containers to hold solid radioactive waste.
• the storage container is only closed by a loosely or detachably arranged lid. This measure makes it possible to remove the lid at any time and, for example, to automatically inspect and control the stored barrels.
• the handling of the individual containers is also possible.
• the design with the loose cover opens up the possibility required to store the individual containers for final storage in accordance with the latest technological knowledge.
• the storage container is preferably stackable for space-saving and stable storage in the interim storage facility.
• this has, for example, a rectangular cross section and on its underside feet and on the top receptacles or guides for the feet of another storage container, as is provided in conventional stacking containers.
• the storage container is designed as a container, the side walls and the bottom of which consist of a concrete structure or of steel.
• the concrete structure can be provided with appropriate reinforcement. Thanks to the concrete structure, both good shielding and adequate mechanical stability for storage can be achieved by simple means and in a cost-effective manner. However, the wall thicknesses are smaller than in comparison to a container designed as a transport container.
• the transport container is designed according to a preferred development for the multiple transport of storage containers. Because the transport container is reusable, only a small number of transport containers is required. Accordingly, the transport container can be very complex and meet the highest security requirements without the costs for the entire warehouse transport system being significantly affected. Appropriately, for the repeated loading and unloading of the transport container, the latter is designed with a container cover, which can be actuated in particular by means of a motor and which can be closed repeatedly.
• the internal dimensions of the transport container are adapted to the external dimensions of the storage container in order to ensure that the storage container is seated in the transport container in a manner that is as precise as possible and therefore secure.
• guides designed in particular in the manner of profiles or strips are preferably provided on the walls of the transport container. Through this, the storage container is as free of play as possible Transport container held.
• the guides preferably have chamfers.
• the transport container is expediently designed as a steel container made of a suitable steel with high shielding performance and high mechanical stability.
• the object is further achieved according to the invention by a method for storing and transporting radioactive waste according to claim 14.
• the advantages and preferred configurations mentioned with regard to the warehouse transport system can also be applied analogously to the method.
• FIG. 1 shows a sectional side view of the storage container with a lid provided for loose support
• FIG. 2 shows the storage container according to FIG. 1 in a further sectional side view
• FIG. 3 shows the storage container according to FIGS. 1 and 2 in supervision with the indication of the cutting planes of FIGS.
• FIG. 4 shows a transport container in a perspective view
• Figure 5 shows the transport container of Figure 4 in a side view with a schematically indicated cab of a truck
• Figure 6 is a highly schematic representation to illustrate the disposal of radioactive waste
• the storage container 2 is designed as a container, the side walls 4 of which, together with the base 6, consist of a uniform concrete structure.
• a lid 8 preferably also made of concrete, is provided with a handle part 9, which is only loosely placed on the side walls 4 to close the storage container 2.
• the storage container 2 has a rectangular outline and is designed to be stackable.
• feet 10 are arranged on the underside of the base 6 at the four corner points.
• the side walls 4 on their upper end face at the four corners each have receptacles 12 or guides into which the feet 10 are inserted when a further storage container 2 is stacked.
• the storage container 2 is provided in the exemplary embodiment for receiving a total of 8 radioactive containers in the form of barrels 14.
• the bottom 6 is profiled on its upper side and in particular has diamond-shaped elevations, so that a total of 8 separate receiving spaces for the barrels 14 are formed.
• the transport container 20 which can be seen in particular from FIGS. 4 and 5, is specially adapted for transport on the power plant site.
• it is designed as a steel container and can be closed with a two-winged container lid 22.
• two motors 26 are provided on an outer end face of the container side wall 24, which are connected via an extendable linkage 28 to each of the wings of the container lid 22 for the reversible opening and closing of the container lid 22.
• Closing and securing devices 30 for the container lid 22 are also arranged on the container side wall 24.
• guide profiles 32 are attached to the container side walls, which have an insertion slope 34 on their upper end face.
• the internal dimensions of the transport container 20 are dimensioned such that the storage container 2 described for FIGS. 1-3 is held between the guide profiles 32 as precisely as possible. The insertion of the storage container 2 is facilitated by the insertion slope 34. These also automatically align and center the storage container 2.
• the transport container 20 is provided for transport by means of a truck 36, of which the driver's cab is shown schematically in FIG. 5.
• the transport container 20 is in this case connected to the truck by suitable screw connections, other detachable connections or also non-detachably by welding.
• the storage container 2 and the transport container 20 are part of a common concept for storing and transporting low and medium-level radioactive waste. The essence of this concept can be seen in the fact that the functions for storage and transport are divided into two different container combinations. Thus, on one side of the storage container 2 is designed only for the function of the storage, in particular in an intermediate storage, not shown here, whereas the function of the transport is fulfilled by the combination of the transport container 20 with the storage container 2 inserted therein.
• the storage container 2 is designed in such a way that when a radioactive waste with a certain initial radioactivity is stored, the permissible maximum radiation dose rate applicable for the interior of the interim storage facility is not exceeded, but not the lower and therefore more stringent maximum permissible radiation dose rate outside the interim storage facility.
• the shielding performance of the storage container 2 is largely determined by the choice of material for the side walls 4, the base 6 and the cover 8, the density of the material and the wall thickness.
• the design of the storage container 2 for the lower requirements within the intermediate storage manifests itself, for example, in the fact that - in each case in comparison to a container which also has to meet the transport requirements -
• the wall thickness is smaller b) if the same material is used, it may have a lower density and
• the storage container 2 is designed as a concrete container.
• the storage container 2 can also consist of a different material or material mix and be designed, for example, as a steel container.
• the higher requirements for transport are expressed, for example, in the lower maximum allowable radiation dose rate already mentioned, as well as the higher requirements for mechanical stability to take into account the higher risk of an accident during transport.
• the higher transport requirements are met by the combination of the transport container 20 with the storage container 2 used therein, wherein the transport container 20 can also be designed in such a way that it alone fulfills the transport conditions, so that, in principle, loose containers of radioactive material can also be found in the transport container 20 Waste materials could be introduced.
• the transport container 20 is used essentially for transport purposes on the power plant site.
• a conditioning device for radioactive waste such as a cementing system 42
• a transport container is provided that meets the requirements of the IAEA.
• the conditioning device 42 is here part of a nuclear engineering application. would be shown 46.
• the interim storage facility 40 can be a special building on the site of the nuclear facility.
• the operation of the nuclear plant 46 in particular for energy generation (nuclear power plant), produces both solid and liquid low and medium-level radioactive waste, which must be disposed of appropriately.
• liquid waste in particular, it is often provided to mix it with a suitable cement mass in the cementing installation 42 and to fill it into the drums 14 already mentioned, in which the mass then solidifies.
• Storage container 2 inserted into the transport container 2, and transported to the intermediate storage 40, where the storage container 2 is lifted out of the transport container 20 again and placed at a storage location provided for this purpose.
• Suitable cranes or lifting devices are provided for handling the drums 14 as well as the storage container 2, which act on the drums 14 or the storage container 2 at suitable locations.
• the lid 8 of the storage container 2 need only be placed loosely. This offers the advantage that the cover 8 can be easily removed during the storage period in the interim storage facility and the barrels 14 located therein can be inspected and checked and, if necessary, for example in the event of a leak, replaced.
• the lid has the handle part 9 on its upper side.
• Another significant advantage of the cover 8, which is only loosely or releasably placed, is that one does not already determine the type of conditioning of the radioactive waste during the intermediate storage, but rather the option for the final conditioning remains open until the radioactive waste be brought into the repository 44. Since the intermediate storage 40 is designed, for example, for a storage time of 30 years, that is to say several decades can pass until it is shipped to the final storage 44, this measure opens up the possibility of taking future technological developments or knowledge into account for the final conditioning. Since the storage container 2 is not only for receiving Barrel 14 can be used, but also for receiving loose radioactive waste, this is of particular advantage. A comparatively simple measure for the conditioning of the repository 44 is to pour the storage container 2 with the barrels 14 embedded therein with a suitable cement mass.

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• Physics & Mathematics (AREA)
• Engineering & Computer Science (AREA)
• General Engineering & Computer Science (AREA)
• High Energy & Nuclear Physics (AREA)
• Refuse Receptacles (AREA)
• Processing Of Solid Wastes (AREA)
• Refuse Collection And Transfer (AREA)

Applications Claiming Priority (2)

Publications (1)

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Family Applications (1)

Country Status (6)

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Citations (3)

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• 2004
  • 2004-02-10 DE DE102004006620A patent/DE102004006620A1/de not_active Withdrawn
• 2005
  • 2005-01-27 WO PCT/EP2005/000786 patent/WO2005078737A1/de active Application Filing
  • 2005-01-27 RU RU2006128982/06A patent/RU2362224C2/ru not_active IP Right Cessation
  • 2005-01-27 EP EP05707031A patent/EP1721322A1/de not_active Withdrawn
  • 2005-01-27 UA UAA200608872A patent/UA87485C2/ru unknown
• 2006
  • 2006-08-10 US US11/502,329 patent/US20100270482A1/en not_active Abandoned

Patent Citations (3)

Non-Patent Citations (1)

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