EP3345190A1 - Installation de stockage final de matière radioactive et procédé de fabrication de celle-ci - Google Patents

Installation de stockage final de matière radioactive et procédé de fabrication de celle-ci

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Publication number
EP3345190A1
EP3345190A1 EP16722620.8A EP16722620A EP3345190A1 EP 3345190 A1 EP3345190 A1 EP 3345190A1 EP 16722620 A EP16722620 A EP 16722620A EP 3345190 A1 EP3345190 A1 EP 3345190A1
Authority
EP
European Patent Office
Prior art keywords
cavity
repository
cavity system
systems
containers
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.)
Withdrawn
Application number
EP16722620.8A
Other languages
German (de)
English (en)
Inventor
Reiner DIEFENBACH
Current Assignee (The listed assignees may be inaccurate. Google has not performed a legal analysis and makes no representation or warranty as to the accuracy of the list.)
Individual
Original Assignee
Individual
Priority date (The priority date 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 date listed.)
Filing date
Publication date
Application filed by Individual filed Critical Individual
Publication of EP3345190A1 publication Critical patent/EP3345190A1/fr
Withdrawn legal-status Critical Current

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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
    • G21F9/00—Treating radioactively contaminated material; Decontamination arrangements therefor
    • G21F9/04—Treating liquids
    • G21F9/20—Disposal of liquid waste
    • G21F9/24—Disposal of liquid waste by storage in the ground; by storage under water, e.g. in ocean
    • 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
    • G21F9/28—Treating solids
    • G21F9/34—Disposal of solid waste
    • G21F9/36—Disposal of solid waste by packaging; by baling
    • B—PERFORMING OPERATIONS; TRANSPORTING
    • B09—DISPOSAL OF SOLID WASTE; RECLAMATION OF CONTAMINATED SOIL
    • B09B—DISPOSAL OF SOLID WASTE NOT OTHERWISE PROVIDED FOR
    • B09B1/00—Dumping solid waste
    • B09B1/008—Subterranean disposal, e.g. in boreholes or subsurface fractures
    • E—FIXED CONSTRUCTIONS
    • E21—EARTH OR ROCK DRILLING; MINING
    • E21D—SHAFTS; TUNNELS; GALLERIES; LARGE UNDERGROUND CHAMBERS
    • E21D13/00—Large underground chambers; Methods or apparatus for making them

Definitions

  • the invention relates to a repository for the storage of radioactive and heat generating 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 Use of a mountain massif as a repository.
  • the spent fuel rods are cooled due to their initially very high activity in a Abklingbecken and then stored in suitable containers for storage and transport of radioactive material for several decades before they are fed to a final storage.
  • Central interim storage facilities are available in Ahaus and Gorleben. They are sized for each 420 large containers.
  • 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 glass chillers specially developed for this purpose are made of 50 cm thick-walled stainless steel and must then first decay for several decades in an interim storage facility until the temperature has dropped sufficiently for them to be sent to a repository.
  • the permanent radiation protection is to be ensured by several barriers.
  • the first barrier is of a technical nature and consists e.g. from the inclusion of the CPR waste in glass jars and / or the packaging in radiation protective containers 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 due to 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.
  • 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 3,000m would provide better demarcation from the biosphere, but would make permanent monitoring and retrieval virtually 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.
  • the invention advantageously provides that the rock formation is a mountain mass in which the first and second cavity systems are interconnected via connecting passages at a plurality of transition points, wherein the first cavity system forms a disposal space in which the containers are free-standing and even with completely filled disposal space are accessible and removable and the second lumen system forms a permanent access enabling system having such a distance from the disposal space that the access system forms a radiation-free area for access to the disposal space at different locations of the first lumen system.
  • At least two technically and functionally independent hollow ⁇ Solutions provided in the massif are spatially connected to each other via connecting passages at a plurality of crossing points, wherein a ers ⁇ tes cavity system forms the Endlagerungsraum and the second cavity system forms an access system comprising a such a distance from the terminal storage space, the access system forms a radiation-free area for the access to the disposal space, which is independent of the first cavity system, to different locations of the first cavity system.
  • 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, which is suitable for the autonomous storage of radioactive material for an indefinite period, but even more so as an intermediate storage and also for low-level radioactive material.
  • both cavity systems are substantially parallel to one another and are basically introduced rising in the rock formation.
  • the parallel arrangement allows any time access to any final repository.
  • the rising arrangement of the cavity systems reliably prevents any accumulation of water and also allows passive forced ventilation. Due to, for example, about a 5% gradient of the floor surface of the final disposal space, an automatic passive discharge of rainwater or other incoming water takes place due to gravity.
  • a passive ventilation system for the disposal space and / or the access system is also created in each case.
  • the passive ventilation is provided by the permanent passive heat dissipation of the CPR in the final storage room by air flow upwards in Kom- Combination with a passive fresh air supply through the lower inlet and outlet opening.
  • the passive ventilation in the first and / or second cavity system can also be effected by the pressure difference or the chimney effect between a lower inlet and outlet opening and an upper outlet opening.
  • the repository is functional after filling without human or technical help. In particular, it is not necessary to keep machines or electronic controls operational.
  • the first and / or second cavity system may each have a lower inlet and outlet opening.
  • the first and / or second cavity system is designed in each case as a continuous channel or tunnel.
  • the inlet and outlet opening can be used for entering or leaving the first or second cavity system.
  • the inlet and outlet openings of the discharge of entering within the first or second cavity system water can be used with simultaneous supply of air from the environment in the first or second 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 first and second cavity system each have a separate upper outlet opening to the outside at the upper end.
  • the outlet opening may have a grid with an adjustable passage cross-section for air, so that the exhaust air flow from the first and / or second cavity system can be controlled by changing the passage cross-section.
  • the passageways are not straight and are substantially horizontal or inclined to the first cavity system.
  • the connecting passages are arcuate. This course of the connecting passages prevents radiation contamination in the event of a leaky container. on the second cavity system.
  • Closing devices such as, for example, doors or locks, which prevent a fluid exchange between the first and second high-room system in the closed state and allow it in the open state, can preferably be provided in the connecting passages.
  • the rock formation is preferably a crystalline rock, e.g. 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.
  • Granite is temperature-tolerant up to 800 ° C, water-insoluble, salt-resistant, very abrasion-resistant and numerous granite formations are permanently weather-resistant.
  • At least the first cavity system serving as a disposal space has a passive venting device which allows heat removal.
  • both cavity systems for disposal and secure access each have the passive ventilation system, which permanently ensures a heat dissipation and fresh air supply independent of active ventilation systems.
  • the second cavity system has e.g. at least a distance of about 10 m, preferably 12 m, from the first cavity system. With such a minimum distance, the radiation safety of the second cavity system is ensured.
  • the second cavity system may be parallel or parallel and offset in height from the first cavity system.
  • the second cavity system is preferably parallel and viewed in the vertical direction with its base at the same height or upwardly offset in height to the first cavity system.
  • both cavity systems can have ventilation channels at predetermined intervals, which preferably extend in an arc shape outward through the rock formation with a gradient. These ventilation channels cause passive forced ventilation of the repository. Due to the special falling and arcuate arrangement of the ventilation channels, no water can penetrate and no radiation can escape 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 in principle have a varying cross-section and can also run polygonally in the spiral.
  • the first cavity system can have a plurality of parallel tunnel systems which are accessible via the second cavity system, preferably from a single tunnel system.
  • the second cavity system can be arranged as an access system to save space, preferably on the inside.
  • At least the first cavity system and possibly also the connecting passages preferably have a width such that containers with radioactive contents, in particular nuclear waste containers, can be transported to any location of the first 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 can be stored in the first cavity system at a distance from the bottom surface. 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.
  • At least the first cavity system may include temperature, radioactive radiation, and visual monitoring monitors.
  • an unmanned transport system may be installed.
  • the flow cross sections of the ventilation channels can be throttled in order to be able to control or regulate the extent of the ventilation or venting.
  • a mountain massif is used as a rock formation, wherein a first and second cavity system are produced in the form of tunnels in the rock formation of the massif and are connected to one another via connecting passages at several transition points.
  • the first cavity system is used as a final storage room for freestanding and accessible even when completely filled final storage space and removable containers.
  • the second lumen system is fabricated at a distance from the first lumen system such that the second lumen system forms a permanent, radiation-free region for access to different locations of the at least one lumen system.
  • the cavity is produced in the form of a cavity complex, whereby at least two technically and functionally independent cavity systems spatially interconnected via connecting passages at several transition points are produced by tunnel boring machines.
  • a first lumen system is used as a disposal space, and a second lumen system serves as an access system for independent access of the first lumen system to different locations of the first lumen system, wherein the second lumen system is made at a distance from the first lumen system such that the second lumen system becomes permanent radiation ⁇ free area forms.
  • 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. Both cavity systems are introduced substantially parallel to each other and basically rising in the mountain massif.
  • the first cavity system can permanently dissipate heat by convection due to the heat released by the freestanding containers and a fresh air supply.
  • the second cavity system may be exposed to a permanent airflow due to the pressure difference between a lower inlet and outlet and an upper outlet.
  • the passageways are not made straight and substantially horizontal or sloping to the first cavity system.
  • the first cavity system are at predetermined intervals, for example, on each floor or all 360 °, arcuately made with slope outwardly extending ventilation channels.
  • the cavity systems are in a preferred development of the inven ⁇ tion spiral, preferably in the manner of a double helix produced.
  • the ventilation of the cavity systems can preferably be regulated by throttling the ventilation cross sections of the ventilation channels.
  • Fig. 1 is a schematic side view of a first embodiment of the
  • FIG. 4 is a schematic side view through the second embodiment of a repository
  • Fig. 8 shows the arrangement of the repository in a mountain massif.
  • the high-active and heat-producing nuclear waste is a monolithic granite, which rises to ei ⁇ ner point above the surrounding surface of the earth addition, disposed of in a repository 1 in a Mountain area 2, for example.
  • 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 two cavity systems 4, 6 is similar in a preferred embodiment shown in Fig. 1 a double helix 16, with two parallel and preferably continuously rising tunnel passages, which are driven upwards into the mountain mass 2.
  • the two initially spatially independent spirals are preferably spatially connected on each floor 8 by a horizontal, arcuate connecting passage 14.
  • the first cavity system 4 forms the final 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 in cross section at the base a width of eg 12 m and in the middle a height of eg 9 m, the slope of the bottom surface 34a is for example about 5%.
  • each projectile 8 Due to the slope of each projectile 8 has a static and radiation safe distance from the adjacent projectile 8.
  • the cross-section of the wall and ceiling area is preferably static, for example, arcuate, eg parabolic executed.
  • the circle, which forms the inner boundary of the first 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, for example, has a diameter of about 174 m. This results, for example, in a tunnel width of the first cavity system 4 of approximately 12 m.
  • the lower inlet and outlet opening 30 to the first cavity system 4 there is a separate inlet and outlet opening 26 to a temporary storage space 28 within the mountain massif 2 for newly arriving container 20 to from there individually via a connecting passage 35 to the first cavity system 4th to transport from where the containers 20 are driven, for example via an automatic (not shown) transport system to the intended storage location.
  • 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 Bergmassivs 2 for technical work, eg for the packaging of radioactive waste, or for a technical control and control center and offices and lounges for the staff.
  • the second, preferably inner cavity system 6 with z. B. parabolic cross section serves as an access system 12, as well as an escape route.
  • This area is a radiation-free area and ensures safe and secure access to any location in the repository for the entire life of the nuclear repository 1, as well as a readily available escape route.
  • the second cavity system 6 is located at a clear distance of at least 6 m, for example about 12 m, preferably within the first cavity system 4.
  • This second cavity system 6 preferably runs substantially parallel to the first cavity system 4.
  • the second cavity system 6 may, for example, in cross section at the base have a tunnel width of about 9 m and in the middle a height of about 6 m.
  • the second cavity system 6 can also, as shown in Fig. 4, offset in height to the first cavity system 4.
  • the base of the second lumen system 6 extends about 11 meters above the base of the first lumen system 4.
  • Vent channels 18 extend from the first lumen system 4 on each floor 8 (each to 360 degrees), e.g. with a gradient of at least 1.5%, preferably in a slight arc, to the outside.
  • 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 second cavity system 6 then ends at the upper end in an outlet opening 41, which leads to the outside.
  • This has the advantage that the base of the second cavity system 6, as shown in FIG. 1, runs at the same height as the base of the first cavity system 4.
  • the passageways 14 in each projectile 8 between the first cavity system raumsystem 4 and the second cavity system 6 may, 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 repository 1 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 first cavity system 4, e.g. a tunnel system, which forms the final final storage space 10 should be at least about 6 m. In principle, 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.
  • This first technical shield is made of preferably corrosion-resistant metal, and ensures adequate and permanent protection against radioactive radiation, so that people in the immediate vicinity can stay safely. Because the first technical radiation shield can be permanently retained in the described repository 1, the radiation protection effect of the rock formation forms an additional second radiation shield. It is important that the spatial structure of the repository 1 is permanently maintained. This is guaranteed in the case of granite for extremely long periods.
  • 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, there are about 10,000 tons of nuclear waste. This results in a number of about 3,000 containers of today's design.
  • the capacity of the repository 1 can be extended if necessary, since the mining machines, e.g. Tunneling 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 the permanent supply of mining equipment with all necessary spare parts remains guaranteed.
  • the mining operations in the first cavity system 4 should preferably at any time have a projection of at least one projectile (360 °) to the end-mounted containers 20 with nuclear waste.
  • a temporary partition between the end-mounted containers 20 and the expansion location in the first cavity system 4 may be provided as additional security.
  • the high-level radioactive residual nuclear waste contained in the containers 20 to be stored and barrels produced by the continuing decomposition processes a lot of heat that is released via the surfaces of the container 20 to the air in the first cavity system 4.
  • This permanently generated heat is the engine for the air flow, which dissipates the heat convection without interruption to the outside. Irrespective of this, there is an uninterrupted flow of air through the present pressure difference in the region of the lower inlet and outlet openings 30, 31, of the repository 1 and the higher-lying ventilation channels 18, 19 and the outlet openings 40, 41 of the repository 1, which due to the height difference in an area with lower air pressure (chimney effect).
  • the vent channels 18, 19 are preferably located on each floor of at least the first and optionally also the second cavity system 4, 6 preferably in each thinnest part of the rock - starting below the highest outer point of the respective cavity system 4, 6 - and are with a slight downward gradient in guided outwards.
  • the outward slope ensures that no water can penetrate from the outside into the cavity systems 4, 6.
  • the arcuate shape of the venting channels 18 is designed so that no direct radiation from the first cavity system 4 can escape to the outside.
  • the diameter or the height of the ventilation 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.
  • the venting channels 19 and the upper outlet opening 41 of the second cavity system 6 can be carried out in the same way.
  • Each vent channel 18, 19 and the upper outlet openings 40, 41 may be in the outer region with a controllable or adjustable slat curtain made of a very stable material, eg carbon fiber composite, equipped to regulate the heat dissipation and fresh air supply in each area of the repository 1.
  • the dimensioning of the vent channels 18 and 19, and the upper outlet openings 40, 41 and the lower inlet and outlet openings 30, 31 are selected so that the circulation or air outlet passive (without fans) works.
  • the constant supply of fresh air through the lower inlet and outlet openings 30, 31 is a direct result of the permanent heat release and the chimney effect.
  • fresh air flows in the region of the lower inlet and outlet openings 30,31 at the base of the cavity systems 4, 6 of the repository 1 in the first and second cavity system 4, 6.
  • the inlet and outlet openings 30, 31 are preferably barred with egg ⁇ nem adjustable passage cross-section of the grid, which can be adjusted by adjusting the passage cross-section of the incoming air flow into the cavity systems 4, 6.
  • the altitude of the repository 1 in a massif 2 reliably prevents flooding by groundwater, a rising sea level, temporary Flooding in rivers or a tsunami.
  • Rainwater, which could seep through gaps in the first or second cavity system 4, 6 is due to the continuous gradient to the lower inlet and outlet openings 30, 31 discharged directly to the base in the access plane 44 or via the venting channels 18, 19 (passive Function, without additional measures such as the use of pumps). Any leaking water has no contact with stored nuclear waste due to the permanent protective effect of the container 20 and therefore can not be contaminated. If necessary, it can be tersucht un ⁇ .
  • the corrosion protection of the containers 20 made of iron, copper or stainless steel for the disposal of highly radioactive and heat-generating atomic waste results from the absence of water. Because of the altitude of the repository 1 flooding is excluded. Small amounts of rainwater could penetrate cracks in the granite of the repository 1 in the first and second cavity system 4, 6. Because of the gradient of the cavity systems 4, 6, these small amounts of rainwater will flow down into the area of the lower inlet and outlet openings 30, 31 at the access level 44 of the cavity systems 4, 6 and can be discharged via the lower inlet and outlet openings 30, 31 become. It is more likely that the small amounts of rainwater will evaporate because of the strong ventilation and the high temperatures and be transported with the exhaust air to the outside. Contamination of the water is not possible.
  • the access and the exit to the final disposal space 10 of the repository 1 are permanently protected 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 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-storing container 20 with HLW waste are in the first cavity ⁇ system 4 in the central region of the leading end storage space 10 preferably made 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 pedestals 32 have, for example, a size of 5 mx 10 m and allow the horizontal storage of the container 20 despite slightly rising bottom surface 34 a.
  • Special vehicles can drive around the platforms 32 360 ° 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 Po ⁇ desten 32 are for example 3.5 m.
  • the technique of transmutation can possibly be used in the future to ⁇ to reduce highly radioactive radiation of nuclear waste 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 high-level 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.
  • 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 connecting passage 35 connection to the lowest starting point of the first cavity system 4, the final final storage space 10.
  • the one individual containers 20 or drums are loaded onto a special vehicle at the starting point of the first cavity system 4 by a special forklift truck. 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 effected, for example, by means of a guide system mounted on the outer wall of the first cavity system 4, similar to a stair lift for people with impaired mobility and / or optically controlled and / or guided by laser.
  • the exemplary dimensions specified in the description of the cavity systems 4, 6 require a total height of approximately seven storeys 8. Of these, five storeys 8 are allocated to the final storage space 10 and one each remains free of containers 20 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 slope of preferably about 5 percent, as best seen in FIGS. 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 additional branches 36, 38, for example in the manner of a bypass, additional disposal space 10 is created.
  • additional branches 36, 38 for example in the manner of a bypass, additional disposal space 10 is created.
  • a plurality of cavity systems 4 ei ⁇ nem single cavity system 6 may be assigned.
  • a plurality of parallel or parallel and height offset preferably spiral end storage rooms 10 could be associated with a corresponding access system 12.

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  • Engineering & Computer Science (AREA)
  • Environmental & Geological Engineering (AREA)
  • Physics & Mathematics (AREA)
  • General Engineering & Computer Science (AREA)
  • High Energy & Nuclear Physics (AREA)
  • Life Sciences & Earth Sciences (AREA)
  • Biodiversity & Conservation Biology (AREA)
  • General Life Sciences & Earth Sciences (AREA)
  • Ocean & Marine Engineering (AREA)
  • Oceanography (AREA)
  • Sustainable Development (AREA)
  • Processing Of Solid Wastes (AREA)

Abstract

Dans une installation de stockage (1) destinée au stockage de matière radioactive dans une formation rocheuse, au moins deux systèmes de cavités (4, 6) étant prévus à distance l'un de l'autre, et un premier système de cavités (4) formant un espace de stockage final (10) destiné à la matière radioactive dans des récipients (20) et le second système de cavités (6) formant un système d'accès (12), il est prévu que la formation rocheuse est un massif montagneux (2) dans lequel les premier et second système de cavités (4, 6) sont reliés entre eux par des couloirs de liaison (14) en une pluralité de points de passage. Le premier système de cavités (4) forme un espace de stockage final (10) dans lequel les récipients (20) sont accessibles et peuvent être retirés indépendamment même quand l'espace de stockage final (10) est totalement plein et le second système de cavités (6) forme un système d'accès (12) qui permet l'accès en permanence et qui se trouve à une distance de l'espace de stockage final (10) telle que le système d'accès (12) forme une zone sans radiation pour l'accès à l'espace de stockage final (10) en différents lieux du premier système de cavités (4).
EP16722620.8A 2015-05-07 2016-05-06 Installation de stockage final de matière radioactive et procédé de fabrication de celle-ci Withdrawn EP3345190A1 (fr)

Applications Claiming Priority (2)

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DE102015208492.2A DE102015208492A1 (de) 2015-05-07 2015-05-07 Endlager für die Lagerung von radioaktivem Material, sowie Verfahren zu seiner Herstellung
PCT/EP2016/060170 WO2016177876A1 (fr) 2015-05-07 2016-05-06 Installation de stockage final de matière radioactive et procédé de fabrication de celle-ci

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CA (1) CA3023762A1 (fr)
DE (1) DE102015208492A1 (fr)
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US11289226B2 (en) * 2017-04-06 2022-03-29 Henry Crichlow Nuclear waste capsule container system
TWI789397B (zh) * 2017-06-05 2023-01-11 美商深絕公司 於地下岩層中儲存危險材料
US10692618B2 (en) 2018-06-04 2020-06-23 Deep Isolation, Inc. Hazardous material canister
US10315238B1 (en) 2018-11-06 2019-06-11 Deep Isolation, Inc. Testing subterranean water for a hazardous waste material repository
US11921427B2 (en) 2018-11-14 2024-03-05 Lam Research Corporation Methods for making hard masks useful in next-generation lithography
TW202036599A (zh) 2018-12-18 2020-10-01 美商深絕公司 放射性廢料貯存系統及方法
US10943706B2 (en) 2019-02-21 2021-03-09 Deep Isolation, Inc. Hazardous material canister systems and methods
US10921301B2 (en) 2019-02-21 2021-02-16 Deep Isolation, Inc. Testing subterranean water for a hazardous waste material repository
US10751769B1 (en) 2019-02-21 2020-08-25 Deep Isolation, Inc. Hazardous material repository systems and methods
US10878972B2 (en) 2019-02-21 2020-12-29 Deep Isolation, Inc. Hazardous material repository systems and methods
CN110005453B (zh) * 2019-04-26 2020-04-28 中铁工程装备集团有限公司 大型地下乏燃料处置库机械化建造方法
EP3908882A4 (fr) 2020-01-15 2022-03-16 Lam Research Corporation Sous-couche pour adhésion de résine photosensible et réduction de dose
DE102020005775B3 (de) 2020-09-22 2021-12-02 Helmut Schmidt Endlager für niedrig und hoch radioaktive Abfälle
CN113903486B (zh) * 2021-10-11 2024-02-23 中国核电工程有限公司 一种用于低中水平放射性废物岩洞处置的方法及结构

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US5850614A (en) * 1997-07-14 1998-12-15 Crichlow; Henry B. Method of disposing of nuclear waste in underground rock formations

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RU2017142622A (ru) 2019-06-07
DE102015208492A1 (de) 2016-11-10
CN108028085A (zh) 2018-05-11
KR20180044230A (ko) 2018-05-02
CA3023762A1 (fr) 2016-11-10
JP2018518688A (ja) 2018-07-12
US20180182505A1 (en) 2018-06-28
WO2016177876A1 (fr) 2016-11-10

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