EP1999759B1 - Method and apparatus for final storage and safe operation of nuclear power stations - Google Patents

Abstract

The creation of a final geological repository in the base region of super-deep bore shaft (10) by magnetically glided, directional melt drilling with cast metal encapsulation (2) for disposing highly radioactive waste material, includes subcritically disposing highly-radioactive material into the borehole shaft. The borehole shaft separates itself from the rest of the shaft after filling by producing the residual heat of the material and/or geo-pressure and/or the self-weight under gravity and/or the molten rock formation from the hot deep-seated rock migrates towards the geocentre. The creation of a final geological repository in the base region of super-deep bore shaft (10) by magnetically glided, directional melt drilling with cast metal encapsulation (2) for disposing highly radioactive waste material, includes subcritically disposing highly-radioactive material into the borehole shaft. The borehole shaft separates itself from the rest of the shaft after filling by producing the residual heat of the material and/or geo-pressure and/or the self-weight under gravity and/or the molten rock formation from the hot deep-seated rock migrates towards the geocentre. The metal encapsulation is a lower cone-shaped shaft segment, which is intended to final repository and whose wall thickness increases downwards from the top. The lateral pressure forces of the deep-seated rock cumulate themselves on the metal encapsulation of the separated cone-shaped final repository segment to downwardly directed pressure forces on the tip of the segment. The super-deep drilling shafts are bored for final disposal of wastes through self-propelled sinking directly at the nuclear power plants, intermediate storage sites and other nuclear-technology based plants. Ingot molds and nuclear fuel rods are stacked one above the other with heat-conducting intermediate spacers to be safely disposed in pressure-resistant carrier units in the borehole shaft by a magnetically-driven gliding system. Liquid lead is filled into the free spaces between the stored materials for reducing the frictional load of the carriers and serves as a heat transfer fluid and moderator for fast neutrons for increasing the heat production. A filled up drill hole section is intended to be closed with a pressure-tight lid (5). The produced residual heat from the subterraneously stored, highly radioactive material leads to an evenly distributed heating in the metal encapsulation of the shaft segment on account of the convection of heat transfer medium (9). The cast metal encapsulation of the borehole shaft above the pressure-tight closed, lower borehole segment is melted over a suitable length to form molten metal by a directional melt drilling method using a magnetically driven gliding vehicle and is separated from the rest of the shaft. The molten metal serves as additional pressure sealing of repository segment (6). On the account of the residual heat production, the own heat of the deep-seated rocks, lateral pressure of the rocks and effect of gravity on the separated final repository segment with a 2 to 3-fold higher mass density than the surrounding rock, a partial melt formation results between the surrounding geological strata and the metal encapsulation of the final repository segment. The formed partial melts act as a guided gliding system between the hot deep-seated rocks and the metal encapsulation and exhibit an accelerated migration towards the geo-center as a consequence of lateral geological pressure effect of gravity on the separated final repository segment. The formation of partial melts is intensified under the supercritical conditions of the fluid in hot deep-seated rocks by the injection of the liquid lead or weak-radioactive into the region of the final repository segment. The liquid lead dissolved in the partial melt follows or overtakes the hot final repository segment during its migration into hotter regions of the center of the earth. The melted-up drill shaft region is filled up with a suitable material. The rest portion of the drill shaft is provided with a suitable metal melt shaft segment tip. The filling of further final repository segments is restarted for a self-propelled sinking prevails. Not only the final disposal of the highly radioactive stock of a nuclear power plant but also its dismantling with direct disposal of the resulting material has to be accomplished at the same site of the super-deep drilling shaft borehole shaft, in such a manner that a bomb-proof connection has to be built from the reactor building and/or reactor, and/or intermediate storage sites to the final repository shaft acting as the disposal site, hermetically separated from the biosphere. The free spaces between the disposed medium and weak-radioactive material is filled with a material, by means of which a corrosion of the final repository segment from the inside is hindered. The top region of the super-deep borehole shaft is filled up in an air and watertight manner. A tunnel that is lined with carbon panels runs from the reactor to a deep-lying basin, which is occupied by high active waste carbon ingot molds with overflow devices and which lies in the decay region of the reactor or the intermediate storage site, so that in the event of a reactor melt, the highly-radioactive melt runs into the ingot molds and has to be disposed by the automated transport system of the final repository device, directly into the medium-filled final repository segment. An independent claim is included for a device for creating a final geological repository in the base region of super-deep bore shafts by magnetically glided, directional melt drilling.

Description

The invention relates to a method for creating a secure repository in a well bore created by melt drilling, which has a solidified by melted metallic Borlochverschalung. The invention further relates to a device for creating secure repository comprising at least one wellbore with a metal casing of a cast. The invention is intended in particular for the disposal of highly radioactive and / or highly toxic material, but is also suitable for the storage of any other materials.

The invention also relates to devices as a safe and cost-effective repository for low and medium-active materials a bomb-proof connection and transport system between reactor or intermediate storage and repository shaft. The invention also relates to devices for the controlled control of a reactor Gaus with meltdown and automated direct disposal of the leaked meltdown.

The sinking of well shafts, in particular so-called super deep well wells with consistently large borehole diameters to the drilling target and in particular at depths up to 20 km or even more, for example, from the publication EP 1 157 187 B1 the same applicant. The method described here can preferably be used to create a wellbore by melt drilling and thereby to provide the wellbore with a seamless Borlochverschalung, in particular made of metal.

For a particular pure molten metal, a metal or a metal mixture is supplied as a drilling medium through conduit elements to be removed by melting borehole bottom, the spoil melt pressed into the particular torn by temperature and pressure environmental rocks and created during drilling by solidifying molten metal a Metalllochlochverschalung ,

For this purpose, the particular pure molten metal emerging from the lowermost conduit element of the metal melting drill rig above the borehole bottom can be guided between the outside of the molten metal boring plant, in particular its lowest conduit element and the borehole inner wall, and solidify there. As drilling progresses, more conduit elements can be attached to the previous element to continuously drill the hole. As line elements, especially in the hot area, such graphite can be used. It can be provided that line elements, in particular in the upper cooled area can work as a magnetic slider, in particular controlled on the metal Borlochverschalung, slide along and preferably both holding forces horizontal and shear forces can exert downward and upward.

The introduction of melted holes is preferably carried out by this known method, but other methods can be used, provided that they are suitable for creating a borehole casing, in particular from a single casting.

The safe disposal of highly radioactive substances is a socially serious problem that is still unsolved worldwide. So far, there is no safe disposal concept in any country, even though hundreds of billions of euros have been spent on searching and testing suitable repositories worldwide.

After 50 years, the nuclear energy community with its scientific and economic potential has never been successful in any country, a sure one Although the unresolved repository problem, in addition to the irrefutable risk of reactor corrosion, has the greatest impact on the decline in the nuclear energy market share of world energy production.

According to current disposal concepts and methods for dismantling nuclear power plants and nuclear facilities their disassembly and disposal of the resulting contaminated material is more expensive than the construction of the plants themselves, so that the search for the 'best possible repository' a high potential savings while increasing security should bring.

Irresponsible procedural proposals such as sinking in deep-sea trenches or shooting to the moon or into space are already prohibited for security reasons and are not up for discussion.

Almost every country with nuclear technology is in the process of developing or building its own repository concepts and devices. The US is working on a repository in the tuff of the Jucca Mountains not far from Las Vegas. Canada, Sweden, Switzerland and others explore hard rock (crystalline) as a repository.

The German repository concept is tailored to salt as a host rock, at least until the beginning of the current moratorium for the Gorleben salt dome, which will run until 2010 at the latest and should be used to search for a 'best possible repository' in different host rocks.

The objective is to have a ready-to-use repository by 2030, whereby it is assumed that all nuclear waste generated by 2080 will be housed in a repository after the decision to phase out the nuclear power plant.

Common to all concepts in the various countries is the approach of a mine-like tunnel system as a central warehouse with large capacity at depths of up to 1000 m depth, which thus remains in the area of the biosphere. There is a danger that groundwater, surface waters and deep waters can penetrate over long periods after tectonic changes and pollute the biosphere.

In Germany, there is a large degree of agreement among those responsible that both the salt dome 'grated' and the ore mine 'Schacht Konrad' At Salzgitter highest is considered as a repository for low and medium radioactive material in question, which accounts for an estimated 280,000 m ³ and 90% of the final radioactive material to 2080, if it remains at the agreed exit.

The search for the 'best possible repository' in Germany, especially for high-level radioactive substances, thus remains a top priority on the agenda and can also become a multi-billion megamarket for the German economy.

The decisive factor for the option of a central repository is the high exploration and construction costs for the shaft construction and the underground tunnels and caverns, since the development costs would therefore have to be made only once. At the same time, according to the current disposal concepts, suitable sites are few and far between.

The risks of transporting and reloading from the transport containers in the repository as well as the high transport costs and the resistance of the population to the transports and to the central location speak against a central repository, because nobody wants to have the long-lived and potentially lethal waste from others in their area.

In the International Agreement on Final Disposal, signed on 1 October 1997, all 42 signatory states agree that the disposal of high-activity, long-lived nuclear energy products outside the biosphere must be safely carried out in deep geological formations along the shortest possible transport routes.

Known methods for the disposal of highly radioactive material in pressure-resistant devices by lowering into the Earth's interior make use of the subduction zone, where the deposited material with the subducting plate disappears in the earth's mantle over millions of years. A possibility of final disposal in subduction zones to be realized with given technology was only given there, as in the US 5,022,788 carried out where the subduction zone is close to the surface and can be reached from the continental crust through well bores or tunnels to store significant quantities can.

The disposal of radioactive material enclosed in pressure-resistant and heat-resistant containers is using conventional drilling technology (KTB) and Shaft construction down to a depth with viscous plutonic rock, as in DE 195 28 496 C1 postulated, technically not possible. The named Continental Deep Well (KTB) in the Upper Palatinate reached its technical and mineral-geological end at 300 ° C rock temperature at 9000 m depth. From 300 ° C and especially in the presence of water, the stability of the rock decreases so much that under the pressure of the side rock breaks the exposed, unverschalte borehole or shaft area from the side. ( GEOSCIENCES Year 13, April 1995, pages 151-153 )

The invention has for its object to overcome these disadvantages and to meet the demand for a 'best possible repository'. The invention is further based on the object to provide a method and a device that provide a safe and cost-effective disposal directly on site and are equally usable in all countries and in particular also still offer the possibility in the case of blowing through a reactor, the reactor structure so to control, without a burden on the environment occurs.

This object is achieved by a method in which endzulagerndes, especially subcritical hochradioaktivives material is deposited in a lower portion of the interconnected wellbore, this lower area is separated after filling from the rest of shaft and this lower area automatically emigrates towards the center of the earth, the wall thickness the metallic well casing of at least one designated as a repository lower wellbill section is performed such that it increases from top to bottom, so that there is a bottom-up substantially conically tapered lower wellbore section.

The object is further achieved in that in a repository at least one lower wellbore section of a interconnected wellbore after filling of repository material, especially in the subcritical state, separated from the rest of the wellbin / disconnected to by self-heat generation and / or rock pressure and / or own weight Gravity effect and / or molten rock formation to sink towards the center of the earth, the well casing of the used as a repository lower well shaft section outside at least substantially forms a conical shape, in which the wall thickness of the casing decreases from bottom to top.

As mentioned above, offers the molten metal drilling method according to EP 1 157 187 B1 a technically feasible drilling method that can be used to rapidly and cost-effectively produce production-ready super deep wells with large, well-defined wellbore diameters down to a depth of 20 km or more in a continuous meltboring process. In the continuous propulsion of the melt drilling rig, in particular by magnetic glides, a seamless die-cast well casing is simultaneously created from acting as a drilling medium molten metal, which serves the magnetic slider as 'reaction rail' and driving tube. These die-casting interconnect wellbores, they are produced by this or another method, are used according to the invention as a repository.

In the case of the continuous molten metal drilling method, there is at no time an exposed, non-counterborder borehole area, since a thick-walled metal casing is built up directly from the molten metal, which also serves as a 'boring head'. The stability of such a interconnected borehole or well depends on the thickness of the metal wall, the prevailing pressure difference between the inner and outer walls and in particular the prevailing temperature. Such a metal-mixed borehole can remain stable up to a minimum of 600 ° C - 700 ° C in the rock temperature range, so that depths of 20 km can be expected in the continental crust. But even under these temperature and pressure conditions, the plutonic rock is not in viscous form but in solid, if ductile form.

Preferably, the hole is created to a depth in which the rock is present in ductile form and in particular already form partial melts whose formation is further enhanced by the self-heat generation of the stored, heat-producing highly radioactive material or in particular under the predetermined temperature and pressure conditions in the hot deep rock, the rock crystals move against a free, solid and especially heavy metal body, on which the gravity of the earth acts stronger than on the surrounding, lighter surrounding rock. Thus, this can advantageously an accelerated emigration of a separated lower wellbore section, which serves as a repository segment effect.

The emigration speed of the entire separated lower borehole shaft section / final repository segment is favored according to the invention in that its outer contour is shaped conically widened downwards, whereby the enormous lateral pressure forces become the vertical thrust force.

This erfindungemäße emigration of the repository segment in the form of a heavy metal body can additionally experience an acceleration by friction reduction due to the increased internal temperature by means of radioactive residual heat generation and / or by a fluid accumulation in the boundary region metal shell / plutonic rock, especially since these fluids under the prevailing temperature and pressure conditions can be supercritical and therefore their friction value drastically reduced.

Advantageously, a repository segment under its gravity, surrounded by the fluid or wetted by a fluid film accelerated to the earth's center to slide, especially in comparison as a glacier slides on his film of water to the valley.

According to the invention, in the lower borehole shaft section, or in particular the highly radioactive material deposited in the shaft deepest, can be filled with a medium, for example with liquid lead as moderator and / or heat and / or pressure compensation medium, or the material to be end loaded can be filled.

A bottommost well section filled in this way can be used as a repository segment according to the invention above the filling of the remaining well shaft by melting down the well casing, in particular the metal casing, e.g. be separated in a range of a few meters and migrates as a whole from the hot plutonic rock in the direction of the center of the earth, especially under self-heat generation and high weight.

The method and the device will be explained in more detail with reference to the single drawing.

According to the invention it can be provided that in the immediate vicinity of nuclear power plants or intermediate storage at least one well, for example a 20 km deep wellbore (10) is drilled according to the described molten metal drilling method.

An upper major portion, e.g. more than three-quarters of the well bore thus created, in particular having a constant diameter throughout, e.g. of preferably more than 0.5 meters, is provided with a well casing, in particular cast-metal thick-walled metal casing, preferably good magnetic permeability, and can be used as a disposal well according to the invention for placing material to be stored in a lower, smaller section, e.g. less than a quarter of the well shaft.

Here, the lower wellbore portion, particularly the lower quarter or less than a final disposal segment (1) e.g. for highly radioactive and / or heat-generating materials or other material. This wellbore section may preferably be arranged in a ductile rock region or in the region of supercritical fluid conditions.

There may also be an overlying portion of the wellbore as a repository for other material, e.g. for low and medium radioactive material, e.g. incurred during the dismantling of a nuclear power plant or other nuclear installation.

According to the invention, the lower section used as a repository segment (1) in the production of the wellbore (10) in the region of the cast metal casing is designed such that the wall thickness in the lower region is greater than in the upper region, for example 0.25 m starts and above with 0 , 05 m ends.

The repository segment (1) can be separated according to the invention as a whole after filling with endzulagernden material and / or segmentally from the rest of the wellbore, the separation of the respective segment of the remaining well can advantageously be done by melting a shaft wall region (4), in particular by radiation energy, which can advantageously come from a laser or a graphite emitter, which can be driven up and down via a magnetic glide device (14) in the wellbore.

The separation according to the invention by melting down a well shaft section directly above the end bearing, e.g. filled with highly radioactive material and preferably molded with, for example, liquid lead Endlagersegments (1) can be preferably carried out so that at the same time for secure closure of the separated Endlagersegments (1) by the resulting molten metal leads, which settles above the Endlagersegmentes and form a metal lid closure (5) can and / or floats directly on the liquid lead and forms a solid metal closure with the remainder of the final storage segment formwork.

The remaining shuttering-free Abschmelzbereich (4) in the well can if necessary. Up to a residual area for a new shaft segment tip (3) with a material (eg Borax) are filled, which promotes the self-burial by emigration from the hot storage rock.

According to the invention, the residual well which is open after separation can be closed with a cast metal filling which serves as a new well segment tip (3) and which is preferred, e.g. reinforced by alloying elements, ensures the self-subsidence process.

The disposal device according to the invention preferably comprises a system (12) safely closed to the biosphere, e.g. a transport tunnel, which connects the final storage shaft (10) to the reactor and / or intermediate storage by a, in particular automated transport device, such as a magnetic slider system.

The invention preferably bombproof, hermetically sealed to the outside transport tunnel (12) between the reactor and repository shaft preferably also allows the construction of a collecting and disposal facility in the case of a reactor melt (13), which greatly reduces the residual risk in the operation of nuclear power plants and significantly longer periods of Nuclear power plants allowed, thereby conveniently the 'golden end' of the production time is extended.

The collecting and disposal device (13) according to the invention for the case of a reactor melt can be immediately included in the construction of new nuclear reactors and thus be optimally designed. In existing nuclear power plants, which are not provided with a bottom protection from graphite cast iron, a withdrawal tunnel can be built below the reactor foundation preferably, which is preferably occupied with graphite crucible and an emerging reactor melt unerringly into a deeper collecting device (15) passes, which preferably also with graphite crucible may be lined and, if necessary, additionally designed with a special crucible made of graphite so that the inflowing reactor melt can be distributed in the available graphite crucibles and can be promoted to the repository after a cooldown on the automated transport system.

The collecting and disposal device according to the invention for the case of a reactor melt (13) can be filled with a medium which is as inert as possible against radioactive radiation, heavier than air and lighter than the reactor melt. Thus, the radiation of the collecting and disposal device (13) is preferably limited, wherein the medium can be pumped out after final storage of the reactor melt and also be stored.

1. 1. Die Niederbringung und Nutzung kostengünstiger Endlagerschächte für insbesondere hochradioaktive Stoffe direkt am Ort der Endstehung und/oder Lagerung erspart hohe Explorationskosten bei der Suche und Erprobung geeigneter Standorte und spart kostbare Zeit, da jeder vorhanden Standort mit Nuklearanlagen für das o. g. erfindungsgemäßen Endlagerverfahren per se geeignet ist und das endzulagernde Material in sichere Tiefen ausserhalb jeglichen Einflusses zur Biosphäre gelangt.
2. 2. Der nukleare Mülltourismus mit hochradioaktivem Material gegen den Widerstand der Bürger hat ein Ende, bzw. kann auf Randbereiche beschränkt werden, reduziert für die Bevölkerung die Strahlenbelastung, das Unfallrisiko und die Entsorgungskosten erheblich.
3. 3. Sichere Endlagerung von hochradioaktiven Brennelementen bis zum hochradioaktiven Inventar der Kernkraftwerke vor Ort durch Selbstversenkung über Bohrschächte von z.B. 15 - 20 km Tiefe in historisch überschaubaren Zeiträumen, unter hermetischem Abschluss zur Biosphäre und mit hoher Kostenreduzierung durch vollautomatisierbare Abläufe bei kürzeren Abklingzeiten, überzeugt Betreiber und betroffene Bevölkerung.
4. 4. Mit der Schaffung von Endlagern an den Hauptkernkraftwerks-Standorten liegen deren Kosten insgesamt erheblich niedriger als bei einer Zentral-Endlager-Lösung. Gleichzeitig wird durch 'burden-sharing' die Verteilung des Problems auf mehrere Standorte, der Widerstand der betroffenen Bevölkerung reduziert, zumal nur die Bevölkerung an den Nuklearanlagenstandorten betroffen ist, die sich ohnehin schon mit der Kernkraft arrangiert hat und deren Risiko und Belastung durch die nicht mehr stattfindenden Nuklearmüll-Transporte erheblich reduziert wird.
5. 5. Die Kombination von direkter Endlagerung Vorort mit einer integrierten Vorrichtung zur Beherrschung eines Reaktorgaus ermöglicht eine erhebliche Verlängerung der Reaktorlaufzeiten und erhöht die Akzeptanz der erfindungsgemäßen Endlagerkonzeption bei Kraftwerksbetreiber, Politiker und betroffener Standortbevölkerung.
6. 6. Die Endlagerung vor Ort bringt für die Standortsbevölkerung betreffender Nuklearanlagen nicht nur die Risiko- und Transportentlastung, sondern schafft mit dem Bau des Endlagers in der Region Arbeitsplätze, die auch langfristig bis zur vollständigen Demontage der Nuklearanlage gesichert sind. Gleichzeitig erhöhen sich die Steuereinnahmen und werden langfristig gesichert.
7. 7. Die Akzeptanz der Bevölkerung mit Nuklearanlagen für Endlagerstandorte Vorort wird insbesondere durch die Selbstversenkung des hochradioaktiven Materials auf nimmer Wiederkehr ins Erdinnere erzielt, da weder der Region noch der nachfolgenden Generation ein unkalkulierbares ,böses Erbe' hinterlassen wird, sondern im Gegenteil auch von der Generation die Lasten der Entsorgung übernommen werden, die auch die Vorteile der Kernenergie genießt.
8. 8. Die Gesamtgesellschaftlichen Vorteile der Endlagerung durch Selbstversenkung an den Nuklearstandorten Vorort über SuperTief-Bohrungen und der damit als Voraussetzung verbundenen Entwicklung des Metallschmelze-Bohrverfahrens zur Einsatzreife werden noch erheblich übertroffen durch die Schaffung eines völlig neuen Multi-Billionen-Marktes aus der neuen Basistechnologie ,Metallschmelze-Bohrverfahren, von der die sichere Endlagerung nur eine der Anwendungen ist.
9. 9. Neben größtmöglicher Sicherheit sind der Zeit- und Kostenfaktor wichtige Argumente für die Endlagerung Vorort: Die Kosten für einen z.B. 20 km tiefen Bohrschacht mit einem Fassungsvermögen von einem m³/m werden auf etwa €200 Mio. geschätzt. Die reine Bohrzeit mit dem kontinuierlich arbeitenden Metallschmelze-Bohrverfahren beträgt dafür etwa ein halbes Jahr, so dass der Rest des Jahres für An- und Abtransport verbleibt und damit pro Jahr mit einer Bohranlage ein 20 km Bohrschacht produktionsfertig erstellt werden kann. Pro Tiefbohrschacht können beispielsweise 5 x 1000 m Endlagersegmente mit einem Endlagervolumen von etwa 5000 m³ genutzt werden. Bei 24000 m³ hochradioaktiver, wärmeentwickelnder Abfälle für die gegenwärtig vorhandenen Kernkraftwerke in Deutschland, wären 5 erfindungsgemäße Endlager notwendig mit einer Gesamtinvestition von € 1 Milliarde. Dieser Betrag ist bereits in den Bau der sich als Endlager ungeeignet erwiesenen Standorte Gorleben und Schacht Konrad investiert worden und muß in dieser Höhe noch einmal investiert werden, bevor sie als Endlager für schwach- und mittelradioaktive Materialien einsatzfähig sind.
10. 10. Die Kosten für die Suche, Erprobung und Bau eines neuen Zentralendlagers zur Lösung für Deutschlands Endlagerproblem wird nach gegenwärtigen Erfahrungswerten mindestens doppelt so teuer wie die erfindungsgemäße Endlagerlösung vor Ort, wobei die Kosten für den Transport und die Kostenersparnis beim Rückbau der Kernkraftanlage nicht eingerechnet sind. Für das Bauzeitszenario zeichnet sich ein ähnliches Bild ab. Für die erfindungsgemäßen Endlager ist unter Einbeziehung der technischen Entwicklung der Magnetgleiter Metallschmelze - Bohranlagen zur technischen Einsatzreife, eine Fertigstellung von 5 Endlagerschächten bis 2020 zu erwarten. Die Fertigstellung eines Zentral-Endlagers nach konventioneller Bergwerksbauweise wohl nicht vor 2030.

The advantages of the repository method according to the invention with a direct repository device on site at the site of nuclear installations by means of well shafts after the molten metal drilling method, compared with known methods and with respect to a central repository, are the following:

1. 1. The deposition and use of low-cost repository shafts for especially highly radioactive materials directly at the place of Endstehung and / or storage saves high exploration costs in the search and testing of suitable locations and saves valuable time, since any existing site with nuclear facilities for the abovementioned repository process per se suitable and the end-bearing material reaches safe depths outside any influence on the biosphere.
2. 2. The nuclear waste tourism with highly radioactive material against the resistance of the citizens has an end or can be limited to marginal areas, reduces the radiation exposure, the accident risk and disposal costs for the population considerably.
3. 3. Safe disposal of highly radioactive fuel elements to the highly radioactive inventory of nuclear power plants on site by self-sinking over wells of eg 15 - 20 km depth in historically manageable periods, under hermetic conclusion to the biosphere and with high cost reduction through fully automated processes with shorter cooldowns, convinced operator and affected population.
4. 4. With the creation of repositories at the main nuclear power plant sites, their overall costs are significantly lower than for a central repository solution. At the same time, 'burden-sharing' reduces the distribution of the problem to several locations, reducing the resistance of the affected population, especially since it only affects the population at the nuclear plant sites, which has already come to terms with nuclear power and its risk and burden more nuclear waste shipments are significantly reduced.
5. 5. The combination of direct disposal on-site with an integrated device for controlling a reactor house allows a considerable extension of the reactor life and increases the acceptance of the final disposal concept according to the invention in power plant operators, politicians and affected local population.
6. 6. On-the-ground disposal does not only reduce the risk and transport burden on nuclear facilities in the area, but also creates jobs in the long-term up to the complete dismantling of the nuclear facility with the construction of the repository in the region. At the same time, tax revenues increase and are secured in the long term.
7. 7. The acceptance of the population with nuclear facilities for repositories Suburb is achieved in particular by the Selbstversenkung of highly radioactive material to never return to the Earth's interior, since neither the region nor the next generation will leave an incalculable, evil legacy ', but on the contrary also of the generation the burden of disposal, which also enjoys the benefits of nuclear energy.
8. 8. The overall societal benefits of self-disposal at the nuclear sites on-site via SuperTief drilling and the associated development of the molten metal drilling process to operational readiness are significantly exceeded by the creation of a completely new multi-trillion market from the new base technology. Metal melt drilling, of which safe disposal is only one of the applications.
9. 9. In addition to the greatest possible safety, the time and cost factor are important arguments for final disposal on the ground: The costs for a 20 km deep well with a capacity of one m ³ / m are estimated at about € 200 million. The pure drilling time with the continuous molten metal drilling process amounts to about half a year, so that the rest of the year remains for transport to and from the plant, so that a 20 km well can be produced ready for production per year with a drilling rig. For example, 5 x 1000 m repository segments with a repository volume of about 5000 m ³ can be used per deep well. With 24,000 m ^{3 of} highly radioactive, heat-generating waste for the currently existing nuclear power plants in Germany, 5 repositories according to the invention would be necessary with a total investment of € 1 billion. This amount has already been invested in the construction of the Gorleben and Schacht Konrad sites, which are unsuitable as repositories, and must be reinvested at this level before they can be used as repositories for low and intermediate level radioactive materials.
10. 10. The costs for the search, testing and construction of a new central warehouse to solve Germany's repository problem is based on current experience at least twice as expensive as the disposal solution according to the invention locally, the cost of transport and cost savings are not included in the dismantling of the nuclear power plant , For the construction time scenario, a similar picture emerges. For the repository according to the invention, including the technical development of the magnetic glider, metal melt - drilling rigs for technical operational readiness, a completion of 5 repository shafts until 2020 expect. The completion of a central repository after conventional mining construction probably not before 2030.

Claims (18)

1. A method of creating a final repository in a borehole produced by a metal fusion drilling method and having a metal borehole lining from a casting continuously formed from the metal melt medium, characterised in that a material for final storage (8) is deposited in a lower area of the borehole shaft (1), this lower area (7) is separated from the rest of the shaft (10) after filling and this lower area (7) migrates automatically toward the centre of the earth, wherein the wall thickness of the metallic borehole lining (2) of at least one lower borehole region (1/7) intended as a final repository is formed so that it increases from the top downward, so that a lower borehole region tapering essentially conically from the bottom upward results.
2. Method according to claim 1, characterised in that the migration is supported by residual heat generation of the highly radioactive material.
3. Method according to one of the preceding claims, characterised in that the borehole is sunk to such a depth that the rock pressure and/or the dead weight under the force of gravity and/or a rock melt formation from the hot plutonic rock supports the migration.
4. Method according to one of the preceding claims, characterised in that the lateral compressive forces of the plutonic rock on the metal jacket of a separated lower borehole region (1/7) accumulate to form downwardly directed compressive forces on the tip (3) of the separated borehole region.
5. Method according to one of the preceding claims, characterised in that at least one borehole for final storage is produced by self-driving directly in situ at nuclear power plants (18) and/or intermediate storage facilities (19) and/or other nuclear facilities.
6. Method according to one of the preceding claims, characterised in that material for final storage (8) is deposited directly into the respectively deepest part of the borehole without contact with the biosphere via a magnetic slide system.
7. Method according to one of the preceding claims, characterised in that a medium is filled in the free spaces (9) between the stored material to relieve the carrier units by uplift and/or as heat transfer media and/or as moderator for fast neutrons to increase the heat production.
8. Method according to one of the preceding claims, characterised in that a filled lower borehole region is closed by a pressure-resistant cover (5).
9. Method according to one of the preceding claims, characterised in that above the closed lower borehole region, the cast metal lining of the borehole (4) is melted over a suitable length by means of a heat source on a magnetic slide melting apparatus and the lower borehole region is thus separated from the rest of the shaft, wherein the metal melt accruing during melting of the borehole lining forms a pressure-resistant plug of the lower borehole region (6).
10. Method according to one of the preceding claims, characterised in that a partial melt formation occurring between the surrounding rock and the jacket of the lower borehole region (2) through residual heat production, autogenously generated heat of the plutonic rock, lateral pressure of the rock and the effect of the force of gravity on the separated lower borehole region (7/1) acts as a slide path between the hot plutonic rock and the jacket of the final repository region (1/7) and under lateral pressure of the rock and/or the effect of gravity on the separated lower borehole region accelerates a migration toward the earth's interior.
11. Method according to one of the preceding claims, characterised in that the fluids dissolved in the partial melt follow and/or precede the hot lower borehole region in the migration into hotter regions of the earth's interior, whereby the safe disposal of the pressed-in fluids is ensured and the migration is additionally accelerated.
12. Method according to one of the preceding claims, characterised in that the rest of the shaft is provided with a shaft plug (3) of metal melt and the method of filling further lower borehole regions is repeated.
13. Method according to one of the preceding claims, characterised in that not only the final storage of the highly radioactive inventory of a nuclear power plant (18), but also the dismantling thereof with direct final storage of the accruing material is carried out in situ in one and the same borehole, such that a connection (12) from the reactor building and/or reactor and/or intermediate storage facility to the borehole, hermetically sealed from the biosphere, is produced.
14. Method according to one of the preceding claims, characterised in that when changing spent nuclear fuel elements and after a short or no intermediate cooling, the spent fuel elements are deposited with a magnetic slide device directly in the cooling medium (9) of the lower borehole region, in order to thus utilise the higher residual heat of the spent fuel elements for quicker self-driving of a lower borehole region.
15. Method according to one of the preceding claims, characterised in that a tunnel (21) runs from the reactor (17) to a low-lying basin (15) lined with graphite ingot moulds with overflow apparatuses (16) and lying in the decay area of the reactor or intermediate storage facility, so that in the event of a reactor meltdown, the highly radioactive melt runs into the basin, the reactor melt being directly deposited via an automated transport system into a lower borehole region as final repository.
16. An apparatus for creating safe final depositories, comprising at least one borehole with a metal borehole lining of a casting, characterised in that at least one lower borehole region (1/7), after filling with final repository material can be separated/is separated from the rest of the borehole, in order to sink toward the centre of the earth by generation of autogenously generated heat and/or rock pressure and/or dead weight under the force of gravity and/or rock melt formation, wherein the borehole lining (2) of the lower borehole region (10) used as final repository outside forms at least essentially a conical shape in which the wall thickness of the lining decreases from the bottom to the top.
17. The apparatus according to one of claims [sic] 16, characterised in that at least one lower borehole region loaded with radioactive material can be filled in the free spaces with a medium, wherein the medium filled in the free spaces between the stored highly radioactive material is used to relieve the weight thereof by uplift and/or as moderator and heat exchanger.
18. The apparatus according to one of claims 16 to 17, characterised in that the transport tunnel (12) hermetically sealed from the outside world can also be used by a nuclear facility as a final repository borehole after the end of the run time of the nuclear facility for direct final storage of the entire contaminated dismantled material.

Images