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EP2555203B1 - Système de forage de stockage pour le stockage d'un combustible nucléaire épuisé et procédé de stockage de combustible nucléaire usé - Google Patents

Système de forage de stockage pour le stockage d'un combustible nucléaire épuisé et procédé de stockage de combustible nucléaire usé 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
German (de)
English (en)
Other versions
EP2555203A1 (fr
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
Original Assignee
Sprava Ulozist Radioaktivnich Odpadu
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Publication date
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Publication of EP2555203A1 publication Critical patent/EP2555203A1/fr
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Publication of EP2555203B1 publication Critical patent/EP2555203B1/fr
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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

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. Un système de puits de stockage destiné au stockage de combustible nucléaire usagé constitué par au moins un couloir horizontal (3), à partir duquel commence au moins un système de stockage, est caractérisé en ce que ledit système de stockage est constitué d'un guide d'orientation de caractérisation du puits de forage (1) et d'un puits de forage de stockage orienté de grand diamètre (2) réalisé dans la ligne médiane dudit guide de caractérisation du puits de forage (1), avec un angle identique en dessous du plan horizontal, dans lequel le guide de caractérisation du puits de forage (1) dépasse par sa longueur le puits de forage de stockage (2), et dans lequel est placé dans ledit puits de forage de stockage (2) au moins un conteneur de stockage (6) destiné à la réception du combustible nucléaire usagé.
  2. Le système de la revendication 1 est caractérisé en ce que l'angle est compris entre 20 et 30 degrés.
  3. Le système de n'importe laquelle des revendications 1 à 2
    est caractérisé en ce que le guide
    de caractérisation du puits de forage (1) a un diamètre compris entre 0,1 et 0,2 m, de préférence 0,12 m, et le puits de forage de stockage (2) a un diamètre compris entre 0,5 et 2 m, de préférence 1,3 m.
  4. Le système de n'importe laquelle des revendications 1 à 3 est caractérisé en ce que le guide de caractérisation du puits de forage (1) est rempli d'un matériau de marquage, de préférence un mélange de sable et de pigment de couleur rouge ou verte.
  5. Le système de la revendication 1 est caractérisé en ce que les systèmes de stockage, commençant à partir du couloir horizontal (3) sont séparés les uns des autres à distance régulière de 20 à 40 m, de préférence 30 m, et les couloirs horizontaux sont disposés en parallèle avec un espacement de 40 à 60 m, de préférence 55 m.
  6. Le système de n'importe laquelle des revendications 1 à 5 est caractérisé en ce qu'il comprend une mine d'accès coupant les sections restantes de la caractérisation des puits de forage (1), constituées par la galerie de manutention (10).
  7. La méthode de stockage du combustible nucléaire usagé dans le système des puits de forage de stockage de la revendication 1 est caractérisée en ce qu'est placé dans le puits de forage de stockage orienté (2), au moyen d'un mécanisme de manutention (4), au moins un conteneur de stockage (6).
  8. La méthode de la revendication 7 est caractérisée en ce que le mécanisme de manutention (4) est un chariot de manutention se déplaçant par gravité avec une corde.
  9. La méthode de la revendication 7 est caractérisée en ce qu'est placé entre chaque conteneur de stockage adjacent au moins un bloc d'espacement (7).
  10. La méthode des revendications 7 à 9 est caractérisée en ce que le conteneur de stockage (6) est placé à l'intérieur d'un super conteneur.
  11. La méthode de la revendication 7 est caractérisée en ce que le conteneur de stockage (6) est placé sur un palier de segment amortisseur (5), au préalable disposé à l'arrière du puits de forage de stockage (2) tandis que l'espace situé entre le conteneur de stockage (6) et la paroi du puits de forage de stockage (2) sera ultérieurement rempli avec deux segments amortisseur (8a, 8b) et/ou un dispositif amortisseur pulvérisé (9).
  12. La méthode de la revendication 11 est caractérisée en ce que le palier de segment amortisseur (5), les segments amortisseur de remplissage (8a, 8b), et le dispositif amortisseur pulvérisé (9) sont constitués d'un type d'argile, la bentonite.
  13. La méthode des revendications 11 est caractérisée en ce que le palier de segment amortisseur (5) a dans la section transversale la forme de l'espace annulaire limité par une section circulaire dotée d'un angle compris entre 110 et 130 degrés, de préférence 120 degrés.
  14. La méthode des revendications 11 et 12 est caractérisée en ce que les segments amortisseur de remplissage (8a, 8b) ont dans la section transversale la forme de l'espace annulaire limité par une section circulaire dotée d'un angle compris entre 110 et 120 degrés, la somme des angles des sections circulaires du palier de segment amortisseur (5) et des segments amortisseur de remplissage (8a, 8b) étant ≤ 360 degrés.
EP12466016.8A 2011-08-04 2012-08-03 Système de forage de stockage pour le stockage d'un combustible nucléaire épuisé et procédé de stockage de combustible nucléaire usé Not-in-force EP2555203B1 (fr)

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

Publications (2)

Publication Number Publication Date
EP2555203A1 EP2555203A1 (fr) 2013-02-06
EP2555203B1 true EP2555203B1 (fr) 2016-11-02

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EP12466016.8A Not-in-force EP2555203B1 (fr) 2011-08-04 2012-08-03 Système de forage de stockage pour le stockage d'un combustible nucléaire épuisé et procédé de stockage de combustible nucléaire usé

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

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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 (fr) * 2020-11-05 2022-05-12 Deep Isolation, Inc. Rapport d'aspect de trou de forage
WO2022159502A1 (fr) 2021-01-19 2022-07-28 Deep Isolation, Inc. Support de conteneurs de déchets dangereux dans des trous de forage

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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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ANONYMOUS: "RD&D Programme 2010 TR-10-63", 1 September 2010 (2010-09-01), pages 1 - 455, XP055174756, Retrieved from the Internet <URL:http://www.skb.se/upload/publications/pdf/TR-10-63.pdf> [retrieved on 20150309] *

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

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