WO2018087244A1 - Moyen de stockage final et/ou intermédiaire pour le stockage de matières radioactives et procédé de fabrication d'un tel stockage - Google Patents

Moyen de stockage final et/ou intermédiaire pour le stockage de matières radioactives et procédé de fabrication d'un tel stockage Download PDF

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Publication number
WO2018087244A1
WO2018087244A1 PCT/EP2017/078794 EP2017078794W WO2018087244A1 WO 2018087244 A1 WO2018087244 A1 WO 2018087244A1 EP 2017078794 W EP2017078794 W EP 2017078794W WO 2018087244 A1 WO2018087244 A1 WO 2018087244A1
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WIPO (PCT)
Prior art keywords
cavity system
cavity
rock
intermediate storage
containers
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PCT/EP2017/078794
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German (de)
English (en)
Inventor
Reiner DIEFENBACH
Original Assignee
Diefenbach Reiner
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Application filed by Diefenbach Reiner filed Critical Diefenbach Reiner
Publication of WO2018087244A1 publication Critical patent/WO2018087244A1/fr

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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
    • G21F9/00—Treating radioactively contaminated material; Decontamination arrangements therefor
    • G21F9/28—Treating solids
    • G21F9/34—Disposal of solid waste
    • 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
    • G21F9/00—Treating radioactively contaminated material; Decontamination arrangements therefor
    • G21F9/04—Treating liquids
    • G21F9/20—Disposal of liquid waste
    • 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
    • G21F9/00—Treating radioactively contaminated material; Decontamination arrangements therefor
    • G21F9/28—Treating solids
    • G21F9/34—Disposal of solid waste
    • G21F9/36—Disposal of solid waste by packaging; by baling

Definitions

  • the invention relates to an end and / or intermediate storage for the storage of radioactive and heat generating and / or toxic material in rock formations, with at least one cavity, which is surrounded by rock material and forms a final storage space for the radioactive material, a method for producing a Repository for the storage of radioactive material, as well as the use of a massif as a final and / or intermediate storage.
  • the spent fuel rods are cooled in a decay tank and then stored in suitable containers for storage and transport of radioactive material for several decades before being disposed of to final storage.
  • Central interim storage facilities are available in Ahaus and Gorleben. They are sized for each 420 large containers. For example, the intermediate containers may remain in an interim storage facility for a maximum of 40 years in Germany. At the latest after this time, they must be transported to a repository. If fuel rods are further processed in a reprocessing plant, highly radioactive fission products are produced which are melted down into glass.
  • the specially developed glass canopies are made of 50 cm thick-walled stainless steel and must then first decay several decades in an interim storage facility until the temperature has dropped sufficiently to be fed to a repository.
  • the permanent radiation protection is to be ensured by several barriers.
  • the first barrier is technical and consists of B. from the inclusion of the HLW waste in glass jars and / or packaging in radiation-protective container made of iron, stainless steel or copper. These containers are so well shielded against radioactive radiation that you can stay safely around them.
  • the geological barriers must be effective, because experts assume that the technical barrier in the known disposal concepts due to corrosion after a certain time is no longer effective. So that the geological barriers can be effective, with all concepts known so far absolute condition is that no water penetrates into the repository. The presence of water would result in radioactive contamination of the repository's surroundings.
  • Clay is a plastic material and therefore has too little static stability. Accurate predictions regarding the spatial changes in a clay formation over a period of 1,000,000 years are not possible. A subsequent recovery of matured barrels with nuclear waste is almost impossible. The heating of the clay by highly radioactive and heat-generating nuclear waste would greatly reduce its static properties as a result of dehydration and cracking as well as the ability to shield against radioactive radiation. Clay formations are therefore excluded for the disposal of highly radioactive and heat-generating nuclear waste.
  • As from the publication: "Department of series 2008: 73” is known (ISBN 978-91-38- 23062-6), granite rock is below the seabed in Sweden and Finland for the underground storage of low and with ⁇ telstark radiating nuclear waste as a deposit used. The deposits are located at a maximum of 100 m below the surface of the earth.
  • Opalinus Clay is favored in Switzerland for the deep storage of highly radioactive nuclear waste despite a water content of 6.6% and a porosity of 18.3% by volume.
  • Tuff is considered in the US for the disposal of highly radioactive nuclear waste. Tuff is relatively light, soft and porous compared to granite.
  • Repositories at a depth of 3,000 m would offer a better demarcation from the biosphere, but would make virtually permanent monitoring and retrievability impossible.
  • the invention is therefore based on the object to provide a safe permanent repository for highly radioactive and heat-generating nuclear waste with permanent monitoring and retrievability of the radioactive waste, and a method for producing the repository.
  • this relates to an end and / or intermediate storage for the final and / or intermediate storage of radioactive material and / or toxic material in a rock formation of a mountain range, wherein at least one cavity system a storage space for the final and / or intermediate storage the material in freestanding containers on pedestals at a distance from the bottom surface in the middle of the room, wherein the at least one cavity system is basically rising and not rectilinear introduced into the massif, and at the bottom has an access and at the upper end by a walk-in opening into Open is open, wherein each individual container is to be arranged in the at least one cavity system such that it remains monitored, accessible and also removable at all times even when the storage space is completely filled.
  • the invention relates to a method for producing an end and / or intermediate storage for the storage of radioactive material or toxic material in containers in a rock formation of a mountain mass, by producing at least one cavity system, which is surrounded by rock material, wherein the at least one Cavity system is used as a storage space for final and / or temporary storage for freestanding containers, wherein the at least one cavity system is made substantially tunnel-shaped in the rock formation of the massif, said at least one cavity system as a storage space for the final and / or temporary storage of freestanding and is also used in fully-filled disposal room accessible and removable containers, the at least one cavity system is basically introduced rising and not straight into the mountain mass and wherein at the bottom of an access and at the top e an opening is made to the outside, the containers standing on pedestals in the middle of the storage room and are permanently accessible and removable
  • the invention advantageously provides that the rock formation is a mountain massif, in which at least one cavity system basically increases. and at least one cavity system forms a final storage space, in which the containers are freestanding and permanently accessible and removable even when the final storage space is completely filled via a non-binding passage.
  • the cavity system has access at the bottom and is open at the top to the outside.
  • the cavity system has in each case at the upper end a separate upper outlet opening to the outside.
  • the cavity system on each floor (in each case after 360 degrees) accessible ventilation channels, which are preferably arcuate and with a slope to the outside. These ventilation channels cause a passive forced ventilation of the storage room and the supply of fresh air.
  • the special falling and arcuate arrangement of the ventilation channels avoids the ingress of water and prevents
  • At least one technically and functionally independent cavity system is provided in the mountain massif.
  • mountain massif is preferably a natural massif.
  • artificially produce the assemblage e.g. made of granite blocks or a mixture of granite blocks or stones with durable concrete. Such a construction could be required where there are no suitable rock formations.
  • the invention relates to a repository, the indefinite storage of the radioactive material to unlimited Duration is suitable, but even more so as an intermediate storage, and ultimately as a warehouse for low-level radioactive material.
  • a plurality of cavity systems extend substantially parallel to one another and are generally introduced rising into the rock formation, wherein the cavity systems are connected to one another via connecting passages at a plurality of transition points.
  • the separate cavity systems have such a mutual distance that each cavity system is suitable for access to the disposal space of the adjacent cavity system at different locations of the cavity systems.
  • the parallel arrangement allows any time access to any final disposal location.
  • the rising arrangement of the cavity systems reliably prevents any accumulation of water and also allows passive forced ventilation. Due to, for example, an approximately 5% gradient of the floor surface of the final disposal space, gravity causes an automatic passive discharge of rainwater or other incoming water.
  • a passive ventilation system for the disposal space of the cavity systems is also created. Passive ventilation is provided by the permanent passive heat dissipation of the CPR in the final disposal room through upward flow of air in combination with a passive supply of fresh air through the lower access.
  • the passive ventilation in the cavity systems can also be done by the pressure difference or the chimney effect between a lower inlet and outlet opening and an upper outlet opening. Overall, the repository after filling without time human or technical help is functional unlimited. Especially It is not necessary to keep machines or electronic controls operational.
  • the at least one cavity system may have as access a lower inlet and outlet opening.
  • the cavity system is preferably designed as a continuous channel or tunnel.
  • the inlet and outlet opening can be used for entering or leaving the at least one cavity system.
  • the inlet and outlet openings of the discharge of incoming water within the cavity system can be used with simultaneous supply of air from the environment into the cavity system.
  • the inlet and outlet openings may be barred, wherein the passage openings of the grid structure may be variable, so that the passing air flow can be regulated.
  • the outlet opening may have a grid with an adjustable passage cross-section for air, so that the exhaust air flow from the cavity system can be controlled by changing the passage cross-section.
  • the passageways between the lumen systems are not rectilinear and are generally horizontal or inclined to the adjacent lumen system.
  • the connecting passages are arcuate. This course of the connecting passages prevents the radiation contamination of the cavity system in the event of a leaky container.
  • Closure devices such as, for example, doors or locks, may be provided in the connecting passages, which prevent a fluid exchange between the high-room systems in the closed state and allow them to be open.
  • the rock formation is preferably a crystalline rock, eg a monolithic granite rock.
  • Granite in comparison with all other natural materials, is particularly suitable for the requirements of a repository for HLW waste because of its homogeneous monolithic structure, high mass, high hardness and flexural strength.
  • C is granite to 800 ° temperature tolerant, water-insoluble, salt ⁇ resistant, high abrasion resistance and numerous granite formations are permanently weatherproof.
  • the cavity system serving as a final storage space has a passive venting device , which enables heat removal.
  • all cavity systems for disposal and secured access each have the passive ventilation system, which permanently ensures heat dissipation and fresh air supply independent of active ventilation systems.
  • a second cavity system has e.g. at least a distance of about 10 m, preferably 12 m, from a first cavity system. At such a minimum distance, any radiation from one of the cavity systems can be adequately shielded.
  • the second and optionally further cavity system can run parallel or parallel and offset in height to the first cavity system.
  • a second or further cavity system runs, for example, preferably parallel and viewed in ver ⁇ tical direction with its base at the same height or upwardly offset in height to the first or adjacent cavity system.
  • Each cavity system may according to a preferred embodiment at predetermined intervals have ventilation channels, which preferably extend arcuately through the rock formation with slope to the outside. These venting channels effect a passive forced ventilation of the repository ⁇ due to the pressure conditions in the cavity system. Due to the special Lumbar and arcuate arrangement of the vent channels can not penetrate water and get no radiation to the outside.
  • the void systems are e.g. spirally shaped as tunneling systems, preferably arranged in the manner of a double helix or multiple helix.
  • the tunnel systems can basically have a varying cross-section and can also run polygonal in the spiral.
  • the cavity system can have a plurality of parallel tunnel systems which are accessible via adjacent cavity systems, preferably from a single tunnel system.
  • a second cavity system can be arranged to save space, preferably innenlie ⁇ ing to a first cavity system.
  • the cavity systems and possibly also the connecting passages preferably have such a width that containers with radioactive contents, in particular nuclear waste containers, can be transported to any location of a cavity system and are accessible there at any time with a filled repository and can also be subsequently removed.
  • the containers containing the radioactive material are located in the first cavity system away from the ground surface, e.g. storable on pedestals. This ensures that no contact of the containers with water can occur.
  • the first cavity system may also include ramifications to increase the disposal space as long as accessibility, drainage, ventilation and retrievability of the containers are guaranteed to be maintained.
  • the at least one lumen system may include temperature, radioactive, and visual monitoring monitors.
  • at least one cavity system an unmanned transport ⁇ system can be installed.
  • the flow cross sections of the ventilation channels can be throttled in order to adjust the scope of the ventilation.
  • a mountain massif is used as a rock formation, wherein at least one cavity system is produced essentially in the form of a tunnel in the rock formation of the mountain massif.
  • the cavity system is used as a final storage room for freestanding and also in completely filled disposal room accessible and removable container.
  • One or more other lumen systems may be manufactured at a distance from a first lumen system such that every other lumen system is sufficiently shielded by the rock formation.
  • the cavity is produced in the form of a cavity complex, wherein for example at least two technically and functionally independent, spatially connected to each other via connection ⁇ transitions at multiple crossing points hollow space systems are prepared by tunneling machines.
  • the cavity systems are used as a final storage space and each cavity ⁇ system can also be used as access to different locations of the adjacent cavity system.
  • These cavities can preferably be produced with tunnel boring machines, wherein the cavity system is not bound to a specific tunnel cross-section and can also contain larger halls or branches as well as bypasses in relation to the tunnel cross-section.
  • Several cavity systems can be introduced substantially parallel to each other and basically rising in the mountain massif.
  • Each cavity system can permanently dissipate heat by convection due to the heat released by the freestanding containers and a fresh air supply.
  • the cavity system may be exposed to a permanent airflow due to the pressure differential between a lower inlet and outlet and an upper outlet.
  • the passageways between the lumen systems are not made straight and substantially horizontal or sloping to the adjacent lumen system.
  • arcuate with slope outwardly extending venting channels are made.
  • the at least one cavity system can, according to a preferred further embodiment of the invention, be produced spirally, preferably in the manner of a helix.
  • the ventilation of the cavity systems can preferably be regulated by throttling the ventilation cross sections of the ventilation channels.
  • 1 is a schematic side view of a first embodiment of the repository in the mountain range
  • FIG. 4 is a schematic side view through the second embodiment of a repository
  • Fig. 7 alternative embodiments of the first cavity system
  • Fig. 8 the arrangement of the repository in a mountain range.
  • the highly radioactive and heat-generating nuclear waste is in a repository 1 in a mountain range 2, z. B. a monolithic granite, which rises at one point beyond the surrounding surface of the earth, finally stored.
  • This arrangement in a mountain range 2 offers significant advantages compared to all other known locations for the disposal of highly radioactive nuclear waste, which are described below.
  • the repository 1 in the form of z. B. two cavity systems 4, 6 is similar in a preferred in FIG. 1 shown embodiment of a double helix 16, with two parallel and preferably continuously rising tunnel passages, which are driven up into the massif 2.
  • the two initially spatially independent spirals are preferably spatially connected to one another on each floor 8 by a horizontal, arcuate connecting passage 14.
  • Both cavity systems 4, 6 form the definitive final storage space 10 for the free-standing containers 20 with highly radioactive and heat-generating nuclear waste (HLW).
  • the space within the first cavity system 4 with a z. B. parabolic cross-section has a width of z. B. 12 m and in the middle of a height of z. B. 9 m, the slope of the bottom surface 34a is for example approx. 5%. Due to the slope of each floor 8 has a static and radiation safe distance from the adjacent floor 8.
  • the cross-section of the wall and ceiling area is preferably static for reasons of arch, z. B. parabolic.
  • the circle, which forms the inner boundary of the second cavity system 4 in horizontal section, for example, has a diameter of about 150 m.
  • the circle that forms the outer boundary of the first cavity system 4 has a diameter of about 174 m. This results, for example, in a tunnel width of the first cavity system 4 of approx. 12 m.
  • the lower inlet and outlet openings 30, 31 of the first and second cavity system 4, 6, and the inlet and outlet opening 26 of the temporary storage space 28 are located substantially on a common access level 44, about which the atomic repository 1 can be achieved at the bottom , Further separate spaces 29 can be created within the massif 2 for technical work, z. B. for the re-packaging of radioactive waste, or for a technical control and control center and offices and lounges for the staff.
  • the second cavity system 6 may provide for the entire life of the nuclear repository 1 the most secure access to any locations of the repository in an adjacent cavity system and provides a readily available escape route.
  • the second cavity system 6 is located at a clear distance of at least 6 m, for example approx. 12 m, preferably within the first cavity system 4.
  • This second cavity system 6 preferably extends substantially parallel to the first cavity system 4.
  • the second cavity system 6 may have, for example, a tunnel width of approx. 9 m and in the middle a height of approx. 6 m or have the same dimensions of the first cavity system 4.
  • the second cavity system 6 may also, as shown in FIG. 4, offset in height from the first cavity system 4.
  • the base of the second cavity system 6 extends, for example, about 11 m above the base of the first cavity system 4. Vent channels 18 lead from the first cavity system 4 on each floor 8 (in each case after 360 °), z. B. with a gradient of at least 1.5%, preferably in a slight arc, to the outside.
  • a modified embodiment if the second cavity system 6 can be completed in its final formation, only a single venting channel with an outlet opening 41 at the upper end of the second cavity system 6 have.
  • the first and second cavity system 6 ends at the upper end in an outlet opening 40, 41, which leads to the outside.
  • the connecting passages 14 in each overall shot 8 between the first cavity System 4 and the second cavity system 6 can, for. B. only each about 12 m long.
  • the repository 1 is at a height level which in any case is well above sea level and e.g. at least 50 m above the level, which can reach the groundwater or flood-bearing rivers in the vicinity of the end-shelf 1 to a maximum.
  • the atomic repository 1 for highly radioactive and heat-generating nuclear waste is located in a mountain range 2 of monolithic granite.
  • the minimum wall thickness of the cavity system 4, 6 e.g. a tunnel system, which forms the final final storage space 10 should be at least about 6 m.
  • the minimum wall thickness in this geometric formation is freely determinable and can also be dimensioned larger.
  • the primary shielding for the radiation through the containers 20 is permanently retained in the final disposal of HLW waste in the repository 1.
  • the spatial structure of the repository 1 is permanently maintained. This is in the case of granite for extremely long time ⁇ rooms guaranteed.
  • the atomic repository 1 for highly radioactive and heat-generating nuclear waste is located in a mountain range 2 of preferably monolithic granite with a large mass, a high hardness and bending tensile strength.
  • the spatial structure of the repository 1 can therefore not be affected by an earthquake. Since the lower inlet and outlet openings 30, 31 and thus also the access level 44 of the repository 1 above the sea level at a height of at least 50 m above the level that can reach the groundwater or flood leading rivers in the vicinity of the repository 1 maximum , the ingress of water due to an earthquake is excluded.
  • the monolithic granite which has at least a wall thickness of about 6 m, because of its large homogeneous mass and high hardness is a permanent protection against any plane crash.
  • the monolithic granite offers by its high and homogeneous mass with a high hardness and bending tensile strength of the highest conceivable static safety. A collapse of the spatial structure is practically excluded.
  • the capacity of the repository 1 is designed according to the endzulagernden amount of highly radioactive and heat-generating nuclear waste. In Germany, until the end of atomic power generation, approx. 10,000 tons of nuclear waste. This results in a number of approx. 3,000 containers of today's design.
  • the capacity of the repository 1 can be extended if necessary, since the mining equipment z. B. tunnel boring machines can remain operational in the repository 1 at the top of the tunnel.
  • the second cavity system 6 and the connecting passages 14 are to be designed in their dimensions so that a permanent supply of mining equipment with all necessary spare parts remains guaranteed.
  • the mining work in the cavity system 4, 6 should preferably at least one projectile of at least one projectile (360 °) to the endgela ⁇ fermented containers 20 m with Atül ül l have.
  • a tem poräre foreclosure between the endlieagerten containers 20 and the extension ngsort in the first cavity system 4 kan n be provided as additional security.
  • the high-level radioactive residual atomic liquid contained in the containers 20 to be stored and barrels produced by the continuing decomposition processes produces much heat which is released via the surfaces of the containers 20 to the air in the first cavity system 4.
  • This permanently generated heat is the engine for the air flow, which, without interruption, conveys the heat convectively to the outside.
  • the venting channels 18, 19 are preferential ⁇ , on each floor, at least of the first a nd optional and the second cavity system 4, 6 preferably each thinnest portion of the rock - starting underhal b of the top outer point of the respective cavity system 4, 6 - and are led outwards with a slight incline in an arc.
  • the outward slope ensures that no external water can penetrate into the cavity systems 4, 6.
  • the arc shape of the venting channels 18 is configured such that does not find a direct radiation from the hollow space ⁇ systems 4, 6 can pass to the outside.
  • the Du diameter or the height of the vent channels 18, 19 and the upper outlet openings 40, 41 is for example 2.20 m, so that they can also be used as an emergency exit.
  • venting channels 19 and the upper outlet opening 41 of the second cavity system 6 can be carried out in the same way.
  • Each breather ⁇ processing channel 18, 19 and the upper outlet openings 40, 41 Kgs NEN a controllable or Adjustab lbaren strip curtain made of a see r len stable material, in ä u m ßeren area it.
  • As carbon fiber be equipped to regulate in each area of the repository 1, the heat dissipation and Frisch airzufu hr.
  • the dimensioning of the venting channels 18 and 19, and the upper outlet openings 40, 41 and the lower inlet and outlet openings 30, 31 are chosen so that the circulation or air outlet passive (without Venti lators) works.
  • the constant fresh air supply through the lower inlet and outlet openings 30, 31 is ei ne direct consequence of the permanent heat release and Kam inwi ⁇ kung.
  • fresh air flows in the region of the lower inlet and outlet openings 30,31 at the base of the hollow space systems 4, 6 of the end bearing 1 in the first and two ⁇ te cavity system 4, 6.
  • the input u nd outlet openings 30, 31 are preferably barred w ith a Adjustab lbaren passage cross section of the Git ⁇ ters, wherein by adjusting the passage section of the air flowing ⁇ current in the cavity systems 4, 6 can be adjusted.
  • the altitude of the repository 1 in a mountain range 2 reliably prevents flooding by groundwater, rising sea levels, temporary floods in rivers or a tsunami.
  • Rainwater which could seep through gaps in the first or second cavity system 4, 6, becomes, due to the continuous gradient, the lower inlet and outlet openings 30, 31 directly at the base in the access level 44 or via the ventilation channels 18 , 19 discharged (passive function, oh ne additional measure ⁇ measures such as the use of pumps). Any escaping water, because of the long-lasting protective effect of the containers 20, has no contact with the atom deposited and can therefore not be contaminated. If necessary, it can be examined.
  • the access and the exit to the final disposal space 10 of the repository 1 are permanently secured by the physical properties of the granite, the altitude of the repository 1, the geometric shape of the double helix with continuous rise, the passive heat and water discharge and the uninterrupted passive fresh air supply.
  • the end-storing container 20 with highly radioactive radioactive nuclear waste freely in the middle of the cavity systems 4, 6 on pedestals 32 is a constant visual monitoring, z.
  • temperature monitoring with sensors and radiation monitoring, z. B. possible with permanently installed measuring devices.
  • a container 20 can be immediately salvaged and secured.
  • Humidity can also be measured without interruption.
  • the repository 1 is dimensioned so that after its complete filling its permanent functioning is ensured without the use of additional technology such as pumps, fans or human activities.
  • the end-holding containers 20 with H LW waste are in the cavity systems 4, 6 in the central region of the leading end storage space 10 on preferably consisting of granite blocks podiums 32, which protrude at least 20 cm above the bottom surface 34a of the first cavity system 4, turned off.
  • the fixed preferably on the bottom surface 34 a podiums 32 have z. B. a size of 5 mx 10 m and allow the horizontal storage of the container 20 despite slightly increasing floor surface 34 a.
  • the platforms 32 can travel around 360 ° and receive and transport any stored container 20 if necessary.
  • Each individual container 20 can in a short time, z. In less than 24 hours.
  • the distances between the pedestals 32 are z. B. 3.5 m.
  • the technique of transmutation may possibly be used in the future to reduce the highly radioactive radiation of nuclear waste more quickly and permanently. This process is currently being further developed. Therefore, there is a chance to retrieve already stored nuclear waste at a later time in order to eliminate or reduce the highly radioactive radiation.
  • the repository 1 described offers the unlimited possibility of retrieval and post-processing of the already stored, highly radioactive radioactive nuclear waste. New arriving, end-storing container 20 are first brought via a separate inlet and outlet opening 26 in the special temporary storage space 28, which is located next to the lower inlet and outlet opening 30 to the cavity system 4, 6.
  • the temporary storage space 28 may serve as a buffer storage of the repository 10 for atomic waste containers 20.
  • This space has a short passage 35 connection to the lowest starting point of the first and / or second cavity system 4, 6, the final final storage space 10.
  • the individual containers 20 or barrels are from a special forklift on a specific vehicle at the starting point of the first and / or second cavity system 4, 6 loaded. This transports the end-storing container 20 independently to the height at which it is to be stored.
  • the steering of the preferably electrically operated vehicle can be carried out, for example, by means of a guide system mounted on the outer wall of the at least one cavity system 4, 6, similar to a stairlift for disabled people and / or optically controlled and / or laser-guided.
  • the container 20 is there from taken over a special individually movable and preferably electrically powered transport vehicle and positioned at the intended final storage area.
  • the exemplary dimensions mentioned in the description of the cavity systems 4, 6 require in the case of a required storage capacity of 10,000 t a total height of about seven storeys 8. Of this, five floors 8 on the final storage space 10 and one of containers 20 remaining free projectile 8 as Safety distance in the lower and upper area as completion.
  • Figures 1 to 3 show a preferred embodiment in which the cavity systems 4, 6 are parallel to each other and each located on the same plane as best shown in Figs. 1 and 3c can be seen.
  • FIGS. 4 to 6 show an alternative embodiment in which the cavity systems 4, 6 run parallel to one another but extend in different planes at different heights.
  • the bottom surface 34a, 34b of the cavity systems 4, 6 each have a preferably continuous pitch of preferably approx. 5 percent on, as best from the Fign. 3b and 6b can be seen.
  • FIGS. 3c and 6c each show a vertical section through the cavity systems 4, 6 of the first and second embodiments, while FIGS. 3a, 3b, 6a and 6b each show a section in a horizontal or vertical plane in the longitudinal direction of the first cavity system 4.
  • FIG. 7 shows variants of the first cavity system 4, in which by branches 36, 38, z. B. in the manner of a bypass, additional Endlagerungs- space 10 is created.
  • the drawings depict repository 1 with two lumen systems 4, 6, it is to be understood that the repository may also consist of a single lumen system or more than two lumen systems. 8 shows the arrangement of the repository 1 in the mountain range 2.
  • the bearing according to the invention described above can be used in its beschrie ⁇ benen variants both as an intermediate and as a repository for radioactive materials. It can also be used for the storage of toxic materials without them having to be radioactive.
  • the invention can also be described alternatively by one of the following feature groups, wherein the feature groups can be combined with one another as desired and also individual features of a feature group can be combined with one or more features of one or more other feature groups and / or one or more of the previously described embodiments are.
  • At least one cavity system forms a storage space for the final and / or intermediate storage of the material in containers, wherein the at least one cavity system is introduced rising and not rectilinear in the rock, and at the lower end of a
  • the containers are arranged in the at least one cavity system in such a way that they are permanently accessible and removable, in particular even when the storage space is completely filled, via a free passage.
  • venting additionally in predetermined intervals venting channels (18), which preferably extend arcuately through the rock with slope to the outside.
  • End and / or intermediate storage according to one of the numbers 1 to 7, wherein the at least one cavity system has branches and / or bypasses and / or chambers.
  • Final and / or temporary storage facility according to one of the numbers 1 to 8, wherein the at least one or each cavity system in the rock above all possible water levels of groundwater, lakes, rivers, potentially high-water rivers, sea water, even in the case of tsunamis in the area of the mountain massif is arranged.
  • the at least one cavity system is basically introduced rising and not straight in the rock
  • the containers are permanently accessible and removable over a non-binding passage of the storage space.
  • Method according to item 10 or 11 wherein via the at least one cavity system due to the heat release by the free-standing container and a fresh air supply permanently heat is dissipated by convection.
  • Method according to one of the numbers 10 to 12 wherein the at least one cavity system is additionally passively ventilated at predetermined intervals.

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  • Engineering & Computer Science (AREA)
  • Environmental & Geological Engineering (AREA)
  • Physics & Mathematics (AREA)
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  • Processing Of Solid Wastes (AREA)

Abstract

Dans un moyen de stockage final et/ou intermédiaire (1) destiné au stockage de matières radioactives dans une formation rocheuse d'un massif montagneux (2), au moins un système de cavité (4) formant un espace de stockage final (10) destiné au matériau radioactif dans des récipients autonomes (20), il est prévu que l'au moins un système de cavité soit introduit dans le massif montagneux fondamentalement de manière ascendante et non linéairement et comporte à l'extrémité inférieure un accès (30, 31) et, à l'extrémité supérieure, une ouverture (40, 41) est ouverte à l'air libre. Les récipients (20) sont disposés dans l'au moins un système de cavité (4) de sorte que, lorsque l'espace de stockage final (10) est totalement rempli, les récipients (20) soient situés sur des piédestaux au milieu de l'espace de stockage et soient accessibles et retirables en permanence.
PCT/EP2017/078794 2016-11-09 2017-11-09 Moyen de stockage final et/ou intermédiaire pour le stockage de matières radioactives et procédé de fabrication d'un tel stockage WO2018087244A1 (fr)

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DE102016222017.9 2016-11-09
DE102016222017.9A DE102016222017A1 (de) 2016-11-09 2016-11-09 Endlager für die Lagerung von radioaktivem Material, sowie Verfahren zu seiner Herstellung

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WO2018087244A1 true WO2018087244A1 (fr) 2018-05-17

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DE (1) DE102016222017A1 (fr)
WO (1) WO2018087244A1 (fr)

Citations (3)

* Cited by examiner, † Cited by third party
Publication number Priority date Publication date Assignee Title
FR2373861A1 (fr) * 1976-12-13 1978-07-07 Hallenius Tore Depot souterrain pour le stockage de matiere radioactive
GB2244171A (en) * 1990-05-15 1991-11-20 Nuclear Technology Waste disposal
EP0568430A1 (fr) * 1992-04-27 1993-11-03 Commissariat A L'energie Atomique Matériau de colmatage, procédé de fabrication de ce matériau de colmatage et procédé de mise en place de ce matériau sur un site de stockage de conteneurs

Patent Citations (3)

* Cited by examiner, † Cited by third party
Publication number Priority date Publication date Assignee Title
FR2373861A1 (fr) * 1976-12-13 1978-07-07 Hallenius Tore Depot souterrain pour le stockage de matiere radioactive
GB2244171A (en) * 1990-05-15 1991-11-20 Nuclear Technology Waste disposal
EP0568430A1 (fr) * 1992-04-27 1993-11-03 Commissariat A L'energie Atomique Matériau de colmatage, procédé de fabrication de ce matériau de colmatage et procédé de mise en place de ce matériau sur un site de stockage de conteneurs

Non-Patent Citations (1)

* Cited by examiner, † Cited by third party
Title
DEPARTEMENTSSERIE, vol. 73, 2008, ISBN: 978-91-38-23062-6

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