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EP2555203B1 - System für Lagerbohrlöcher zur Lagerung eines verbrauchten Kernbrennstoffes und Verfahren zur Lagerung des verbrauchten Kernbrennstoffes - Google Patents

System für Lagerbohrlöcher zur Lagerung eines verbrauchten Kernbrennstoffes und Verfahren zur Lagerung des verbrauchten Kernbrennstoffes Download PDF

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Publication number
EP2555203B1
EP2555203B1 EP12466016.8A EP12466016A EP2555203B1 EP 2555203 B1 EP2555203 B1 EP 2555203B1 EP 12466016 A EP12466016 A EP 12466016A EP 2555203 B1 EP2555203 B1 EP 2555203B1
Authority
EP
European Patent Office
Prior art keywords
storage
borehole
characterization
nuclear fuel
spent nuclear
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.)
Not-in-force
Application number
EP12466016.8A
Other languages
English (en)
French (fr)
Other versions
EP2555203A1 (de
Inventor
Jiri Slovak
Marketa Dohnalkova
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.)
SPRAVA ULOZIST RADIOAKTIVNICH ODPADU
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Sprava Ulozist Radioaktivnich Odpadu
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Publication of EP2555203A1 publication Critical patent/EP2555203A1/de
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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
    • G21F9/04—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

Definitions

  • the invention is directed to the system of storage boreholes for storage of the spent nuclear fuel or high activity wastes and a method of this storage.
  • the spent nuclear fuel or high activity wastes hereinafter only "spent nuclear fuel", intended for disposal is stored into the so called deep repositories.
  • the spent nuclear fuel is before its storage in these deep repositories placed into special storage containers.
  • there are used two basic principles of deep repositories - vertical or horizontal storage boreholes and eventually a combination of them.
  • the method of the storage into vertical storage boreholes assumes the storage of the spent nuclear fuel in storage containers into boreholes with filling of the intermediate space between the container and the rock with a bentonite buffer layer.
  • the Chinese patent CN 101971268 describes storage of a spent nuclear fuel into a vertical borehole by means of cables reaching upto the bottom of the borehole. Storage containers are stored in the space bounded by theses cables.
  • a Russian patent RU 2212720 describes storage of the spent nuclear fuel into 100 m deep vertical boreholes in special repositories equipped with a steel lining with a concrete filling including concentric steel casings.
  • the Japanese patent JP2008073572 describes a method of storage of the spent nuclear fuel into a horizontal borehole and its back removal by means of a parallel horizontal borehole located under the level of the storage borehole. Both parallel boreholes are mutually interconnected with perpendicular removing openings.
  • a drawback at horizontal boreholes is the unsuitability for back removal of the already stored fuel or financial and mechanical demand, respectively, of eventual removing.
  • the next drawback of these systems is the unsuitability of placing these boreholes in heterogeneous rock mass due to the stability of the borehole from the time of building upto the end of the storage period.
  • An object of the present invention is the system according to claim 1 of storage boreholes for storage of a spent nuclear fuel 3DD - Three dimensional disposal and the method according to claim 7 of storage of the spent nuclear fuel into storage boreholes, which eliminates the above given drawbacks of the existing state of the art.
  • the system of storage boreholes for storage of a spent nuclear fuel is formed of at least one horizontal corridor, from which at least one storage system comes out, which system consists of a guide characterization borehole and of an angling storage borehole made in its centre line, where storage containers are located.
  • the guide characterization borehole and the angling storage borehole are boreholes with an identical angle ranging from 20 to 30 degrees, while the guide characterization borehole exceeds by its length the storage borehole.
  • the diameter of the guide characterization borehole is in the range from 0.1 to 0.2 m, preferably 0.12 m and the diameter of the angling storage borehole is in the range from 0.5 to 2 m, preferably 1.3 m.
  • the guide characterization borehole can be filled with a marking material e.g. a mixture of a sand with a colour pigment in the red or green colour for easy localization of the storage borehole in case of a back removal of the stored spent nuclear fuel.
  • the building process of the system proceeds so that first the characterization borehole is drilled, which serves for a detail verification of rock quality for storage. Consequently, the storage borehole is drilled in the centre line of the characterization borehole.
  • the access mine working can be constructed also with a long time delay from For back removal of storage containers, it is possible to build an access working e.g. a handling gallery intersecting the remaining sections of the characterization boreholes, along which the borehole for removal of containers with the stored spent nuclear fuel will be drilled.
  • the access mine working can be constructed also with a long time delay from the time of storage of the spent nuclear fuel into storage boreholes.
  • the guide characterization borehole serves for localization of the storage borehole and the consequent drilling of the borehole to remove the container with the stored spent fuel.
  • the system preferably includes more horizontal corridors arranged parallelly in the spacing from 40 to 60 m, preferably 55 m, where at regular sections from 20 to 40 m, preferably 30 m, storage systems are built, which consist of a guide characterization borehole and an angling storage borehole.
  • the method of storage of the spent nuclear fuel to the system stipulates in the storage of at least one storage container into the angling storage borehole (preferably more storage containers) by means of a handling mechanism.
  • the handling mechanism by which the transport of individual components of the storage system to the bottom of the storage borehole takes place, can be a material handling truck moving by gravity on a rope.
  • the storage container can be located in a super-container, which includes an external overwrap with engineering barriers including a buffer.
  • the cohesion of the super-container is secured by an external basket with a cover, which is a cylindrical vessel of a perforated sheet, while openings of the perforation form 60% of the overwrap surface of the super-container.
  • a cover which is a cylindrical vessel of a perforated sheet, while openings of the perforation form 60% of the overwrap surface of the super-container.
  • the individual parts of the buffer e.g. bentonite blocks (moulds) and in the centre, there is located the storage container.
  • the storage container can be placed into a storage borehole on a bearing buffer segment.
  • the bearing buffer segment is preferably formed by a bentonite block and in its section it has a form of a part of an annular space limited with a section of a circle with the angle from 110 to 130 degrees, preferably 120 degrees.
  • the whole process is finished then by running in and consequent hydraulic storage of two filling buffer segments into the place of storage, and/or by spraying of the free space around the storage container with a sprayed buffer, which is eventually gradually compacted by a special compacting mechanism.
  • the filling buffer segments are preferably formed of bentonite blocks and have in the section the shape of a part of an annular space limited with a section of a circle with an angle ranging from 110 to 120 degrees.
  • the sum of angles of sections of a circle of the bearing buffer segment and filling buffer segments is ⁇ 360 degrees.
  • the buffer is a material of group clay, bentonit, having the ability to carry off the heat from the radioactive waste to the surrounding rocks, to inhibit fading of radionuclides, at the same time to protect the storage container against mechanical pressure influences.
  • the remaining free space between the segments, the storage container and the wall of the storage borehole is consequently filled with a sprayed buffer.
  • the sprayed buffer is of the group clay, bentonit.
  • the distance block is preferably formed of circular bentonite block.
  • an access working (handling gallery) For back removal of storage containers, it is possible to built, independently of horizontal corridors and storage systems, an access working (handling gallery).
  • the access mining work can be constructed in undisturbed rocks also in a large time delay from the time of storage of the spent nuclear fuel to storage boreholes.
  • the guide characterization borehole serves for localization of the storage borehole.
  • the handling gallery locks on the marking material of the guide characterization borehole, it is built along it an access removing borehole to the lowest stored storage container.
  • the removal then consists of releasing of pressure conditions around the storage container for example by drilling or washover and consequent catching of the storage container into a suitable instrument and its withdrawal to the handling gallery and its loading on the transport mean and transport out of the mine.
  • the advantage of this method is the lower demand on the area in the underground part of the deep repository, easy handling using the gravity forces at building of the borehole and storage of the spent nuclear fuel, but also the possibility of its back removal.
  • the selected angle is sufficient for movement of the storage mechanism by action of the horizontal component of the gravity force and at the same time it reduces loading of the handling rope by transmission of the vertical component into the underlying rock.
  • the advantage of the system of storage boreholes according to the invention is, that the angle of the storage borehole ensures a stabile position of storage containers even in case , that they will be at the back removal released from the pressure locking of the buffer.
  • Another advantage is the possibility to build an access working in heterogeneous rock mass and the possibility of a back removal of the fuel in a large time delay after closing of the deep repository.
  • the system of storage boreholes for storage of the spent nuclear fuel shown in Fig. 1 consisting of a horizontal corridor 3, from which starts a storage system consisting of an angling guide characterization borehole 1 and of an angling storage borehole 2 with identical angle of 30 degrees.
  • the guide characterization borehole 1 has a diameter of 0.12 m, with its length it exceeds the storage borehole 2 and it is filled with a marking material, in this case a mixture of sand with a colour red pigment.
  • the storage borehole 2 has a diameter of 1.3 m and inside it, there are placed storage containers 6 and between them is placed a distance block 7.
  • the storage system includes an access mine working, which is the handling gallery 10.
  • the storage container 6 is placed inside a super-container.
  • the system of storage boreholes for storage of the spent nuclear fuel is carried out as in the example 1 except that the storage container 6 is placed on the bearing buffer segment 5.
  • the space between the storage container 6 and the wall of the storage borehole 2 is filled with two filling buffer segments 8a, 8b, as shown on the Fig. 2 .
  • the storage container 6 is placed on the bearing buffer segment 5 and the space between the storage container 6 and the wall of the storage borehole 2 is filled with a sprayed buffer 9, as shown on the Fig. 3 .
  • the sprayed buffer (9) is eventually gradually compacted by a special compacting mechanism.
  • horizontal corridors 3 are arranged parallelly with spacing of 55 m and from them, in regular sections per 30 m, there start storage systems consisting of a guide characterization borehole 1 and of an angling storage borehole 2, built in its centre line.
  • the method of storage of the spent nuclear fuel to the system of storage boreholes enables a long-term storage of the spent nuclear fuel or of high active wastes, which is easy to handle, undemanding in terms of a structure of the underlying rock, and enables back removal of the fuel.

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

Claims (14)

  1. Ein System von Lagerbohrlöchern für Lagerung des abgebrannten Kernbrennstoffes bestehend aus mindestens einem waagerechten Korridor (3), wovon mindestens ein Lagerungssystem beginnt, dadurch gekennzeichnet, dass das genannte Lagerungssystem aus einem schrägen charakteristischen Führungsbohrloch (1) und einem schrägen Lagerbohrloch (2) mit größerem Durchmesser gefertigt in der Mittellinie vom genannten charakteristischen Bohrloch (1) mit einem identischen Winkel unter der waagerechte Ebene besteht, worin das charakteristische Führungsbohrloch (1) mit seiner Länge das Lagerbohrloch (2) überschreitet und worin im genannten Lagerbohrloch (2) mindestens ein Lagerbehälter (6) für Aufnahme vom abgebrannten Kernbrennstoff platziert ist.
  2. Das System des Anspruchs 1 dadurch gekennzeichnet, dass der Winkel im Bereich von 20 bis 30 Grad liegt.
  3. Das System des jeden von den Ansprüchen 1 bis 2
    dadurch gekennzeichnet, dass das charakteristische
    Führungsbohrloch (1) einen Durchmesser zwischen 0,1 und 0,2 m, vorzugsweise 0,12 m, hat und das Lagerbohrloch (2) einen Durchmesser zwischen 0,5 und 2 m, vorzugsweise 1,3 m, hat.
  4. Das System des jeden von den Ansprüchen 1 bis 3 dadurch gekennzeichnet, dass das charakteristische Führungsbohrloch (1) mit Markierungsmaterial, vorzugsweise mit einem Gemisch von Sand und einem Farbpigment der roten oder grünen Farbe, gefüllt ist.
  5. Das System des Anspruchs 1 dadurch gekennzeichnet, dass die vom waagerechten Korridor (3) beginnenden Lagerungssysteme in regelmäßigen Abständen von 20 bis 40 m, vorzugsweise 30 m, voneinander getrennt sind und die waagerechten Korridore mit Abständen von 40 bis 60 m, vorzugsweise 55 m, angeordnet sind.
  6. Das System des jeden von den Ansprüchen 1 bis 5 dadurch gekennzeichnet, dass es einen Zugangsabbauraum enthält, der die übrigen Abschnitte des charakteristischen Bohrlochs (1) durchschneidet, das die Handhabungsrundgang (10) ist.
  7. Die Methode der Lagerung des abgebrannten Kernbrennstoffes ins System der Lagerbohrlöcher des Anspruchs 1 dadurch gekennzeichnet, dass mindestens ein Lagerbehälter (6) in das schräge Lagerbohrloch (2) mit Hilfe von einem Handhabungsmechanismus (4) gestellt wird.
  8. Die Methode des Anspruchs 7 dadurch gekennzeichnet, dass das Handhabungsmechanismus (4) ein Materialtransportwagen ist, der sich durch Schwerkraft am Seil bewegt.
  9. Die Methode des Anspruchs 7 dadurch gekennzeichnet, dass mindestens ein Distanzstück (7) zwischen jeden nebeneinanderliegenden Lagerbehälter gestellt wird.
  10. Die Methode der Ansprüche 7 bis 9 dadurch gekennzeichnet, dass der Lagerbehälter (6) in einen Supercontainer gestellt wird.
  11. Die Methode des Anspruchs 7 dadurch gekennzeichnet, dass der Lagerbehälter (6) auf ein tragendes Puffersegment (5) gestellt wird, früher auf den Boden des Lagerbohrloches (2) gelegt wird, während der Raum zwischen dem Lagerbehälter (6) und der Wand des Lagerbohrloches (2) folglich mit zwei füllenden Puffersegmenten (8a, 8b) und/oder mit einem gesprühten Puffer (9) gefüllt wird.
  12. Die Methode des Anspruchs 11 dadurch gekennzeichnet, dass das tragende Puffersegment (5), die füllenden Puffersegmente (8a, 8b) und der gesprühte Puffer (9) aus der Gruppe Ton, Bentonit gefertigt sind.
  13. Die Methode des Anspruchs 11 dadurch gekennzeichnet, dass das tragende Puffersegment (5) im Querschnitt eine Form von einem Teil des ringförmigen Raumes hat, der durch einen Abschnitt des Kreises mit einem Winkel von 110 bis 130 Grad, vorzugsweise 120 Grad, begrenzt ist.
  14. Die Methode der Ansprüche 11 und 12 dadurch gekennzeichnet, dass die füllenden Puffersegmente (8a, 8b) im Querschnitt eine Form von einem Teil des ringförmigen Raumes haben, der durch einen Abschnitt des Kreises mit einem Winkel von 110 bis 120 Grad begrenzt ist, während die Summe der Winkel von Abschnitten des Kreises des tragenden Puffersegment (5) und der füllenden Puffersegmente (8a, 8b) < 360 Grad beträgt.
EP12466016.8A 2011-08-04 2012-08-03 System für Lagerbohrlöcher zur Lagerung eines verbrauchten Kernbrennstoffes und Verfahren zur Lagerung des verbrauchten Kernbrennstoffes Not-in-force EP2555203B1 (de)

Applications Claiming Priority (1)

Application Number Priority Date Filing Date Title
CZ20110475A CZ2011475A3 (cs) 2011-08-04 2011-08-04 Systém ukládacích vrtu pro ukládání vyhorelého jaderného paliva a zpusob ukládání vyhorelého jaderného paliva

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EP2555203A1 EP2555203A1 (de) 2013-02-06
EP2555203B1 true EP2555203B1 (de) 2016-11-02

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EP (1) EP2555203B1 (de)
CZ (1) CZ2011475A3 (de)
ES (1) ES2609602T3 (de)
HU (1) HUE030638T2 (de)

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RU2649656C1 (ru) * 2017-06-29 2018-04-05 Российская Федерация, от лица которой выступает Государственная корпорация по атомной энергии "Росатом" Способ обнаружения и определения параметров фрагментов ядерного топлива в кладке остановленного уран-графитового реактора
US10692618B2 (en) 2018-06-04 2020-06-23 Deep Isolation, Inc. Hazardous material canister
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
US10878972B2 (en) 2019-02-21 2020-12-29 Deep Isolation, Inc. Hazardous material repository systems and methods
US10943706B2 (en) 2019-02-21 2021-03-09 Deep Isolation, Inc. Hazardous material canister systems and methods
WO2022099051A1 (en) * 2020-11-05 2022-05-12 Deep Isolation, Inc. Drillhole aspect ratio
WO2022159502A1 (en) 2021-01-19 2022-07-28 Deep Isolation, Inc. Supporting hazardous waste canisters in drillholes

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US5863283A (en) * 1997-02-10 1999-01-26 Gardes; Robert System and process for disposing of nuclear and other hazardous wastes in boreholes
US6238138B1 (en) * 1997-07-14 2001-05-29 Henry Crichlow Method for temporary or permanent disposal of nuclear waste using multilateral and horizontal boreholes in deep islolated geologic basins
US20100105975A1 (en) * 2008-10-12 2010-04-29 James Russell Baird Nuclear Assisted Hydrocarbon Production Method

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ES2609602T3 (es) 2017-04-21
CZ2011475A3 (cs) 2013-02-13
HUE030638T2 (en) 2017-05-29
EP2555203A1 (de) 2013-02-06

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