EP0093671A1 - Geologische Anlage zur Lagerung von radioaktivem Material, insbesondere in verglaster Form - Google Patents

Geologische Anlage zur Lagerung von radioaktivem Material, insbesondere in verglaster Form Download PDF

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Publication number
EP0093671A1
EP0093671A1 EP83400871A EP83400871A EP0093671A1 EP 0093671 A1 EP0093671 A1 EP 0093671A1 EP 83400871 A EP83400871 A EP 83400871A EP 83400871 A EP83400871 A EP 83400871A EP 0093671 A1 EP0093671 A1 EP 0093671A1
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EP
European Patent Office
Prior art keywords
galleries
waste
geological
plane
wells
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.)
Granted
Application number
EP83400871A
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English (en)
French (fr)
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EP0093671B1 (de
Inventor
Guy Courtois
Claude Jaouen
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.)
Commissariat a lEnergie Atomique et aux Energies Alternatives CEA
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Commissariat a lEnergie Atomique CEA
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Publication of EP0093671A1 publication Critical patent/EP0093671A1/de
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Publication of EP0093671B1 publication Critical patent/EP0093671B1/de
Expired legal-status Critical Current

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    • G—PHYSICS
    • G21—NUCLEAR PHYSICS; NUCLEAR ENGINEERING
    • G21F—PROTECTION AGAINST X-RADIATION, GAMMA RADIATION, CORPUSCULAR RADIATION OR PARTICLE BOMBARDMENT; TREATING RADIOACTIVELY CONTAMINATED MATERIAL; DECONTAMINATION ARRANGEMENTS THEREFOR
    • G21F9/00—Treating radioactively contaminated material; Decontamination arrangements therefor
    • G21F9/28—Treating solids
    • G21F9/34—Disposal of solid waste

Definitions

  • the present invention relates generally to techniques for preserving radioactive materials from used fuel elements after they have been discharged from a reactor.
  • Fissile materials which have remained in a nuclear reactor such as for example an enriched uranium reactor cooled with pressurized light water, are depleted in U 235 and correspondingly enriched in plutonium at the same time as waste is created.
  • a nuclear reactor such as for example an enriched uranium reactor cooled with pressurized light water
  • reprocessing operations are frequently carried out on such used fuel elements which essentially allow the separation of uranium depleted in isotope 235 and the plutonium formed as well as the packaging of the waste in a safe form.
  • the residual products which cannot be used and which contain a significant proportion of highly radioactive materials are then subjected to vitrification operations.
  • Tables 1 and 2 which follow give respectively for the fission products and for the actinides, the masses and powers of the radioactive nuclei obtained from the reprocessing of a ton of uranium contained in fuel elements for a light water nuclear reactor, the reprocessing of which was carried out three years after the fuel was unloaded.
  • the radioactive waste thus vitrified is commonly stored in France in the form of a compact cylindrical mass with a volume of 220 liters in a metal container whose wall has a thickness of 5 mm, whose diameter is 430 mm and the height of 1660 mm.
  • Such containers spontaneously heat up to high temperatures; to ensure good preservation with a sufficient safety limit, it was decided not to exceed 200 ° C at the container surface and 450 ° C at the heart of the glass on the axis of the container.
  • Such a container known per se is shown by way of indication in Figure 1 attached.
  • the object of the present invention is precisely to jet a geological storage facility which allows, thanks to relatively simple means, to carry out the two previous conservation periods successively on the same site.
  • the subject of the invention is a process for the disposal of radioactive waste, in particular vitrified waste, characterized in that a first interim storage under ventilation is carried out in the same geological site and successively over time. air by natural convection, then, after stopping this ventilation and closing the site with a geochemical barrier, a final deposit ensuring the complete decrease in the radioactivity of this same waste.
  • the process which is the subject of the invention therefore consists in carrying out the two operations of interim storage and final disposal in a geological installation with sufficient depth and nevertheless capable of being ventilated by natural convection of fresh air coming from the ground surface and placed in motion only by the calorific energy released by radioactive waste buried in the ground.
  • the radioactive decay having reached the desired rate, there is no longer any risk in considering final storage in situ, the site is completely and definitively closed off, of course, stopping the previous ventilation.
  • the galleries in the second lower plane are used to supply fresh air from the surface and to evacuate the hot air that has circulated in the installation; the fact that these galleries are inclined at an angle a to the common direction of the galleries in the foreground makes it possible to arrange the vertical storage wells between the axis of the galleries in the foreground and the lateral niches, adjacent to the galleries in the second plane, in which a support resting on the surface of the ground ensures the seat and the stability of the vitrified active waste containers stacked in said vertical storage wells from the upper galleries in the foreground.
  • These vertical wells, in which the release of heat due to the storage of waste takes place, are also traversed by a hairpin in the ascending-descending direction by the air flow of ventilation by natural convection.
  • the angle a of inclination of the galleries of the second plane relative to the galleries of the foreground is equal, preferably to one of the two values 30 ° and 45 °, the regular geometric network of vertical sinks of storage between the two planes of galleries being either with hexagonal meshes, or with square meshes.
  • the arrival of fresh air and the departure of hot air at the level of the galleries in the second plane takes place via a belt of two peripheral galleries, surrounding the galleries in the second plane, and communicating with they.
  • the radioactive waste is distributed, inside each vertical storage well, in tubes occupying the periphery of the well and traversed by ascending fresh air, the hot air descending in an empty central tube, the base of each peripheral tube being able to include a fall damping device and all the tubes resting on a cast iron base support filled with concrete and placed in the center of a lateral niche.
  • the vertical storage wells are closed, at their outlet in the galleries in the foreground, by a metal plate or plug ensuring the protection of personnel against radiation without preventing the vehicle traffic.
  • the first upper gallery plane can be located depending on the nature of the terrain between 300 and 1000 meters and the vertical distance separating them from the second lower gallery plane can be of the order of 20 to 40 meters but preferably 25 to 30 meters, which makes it possible to superimpose in the preceding tubes 10 to 15 layers of each 6 vitrified containers with a height of approximately 85 cm each.
  • the vertical storage wells 5 extend vertically in which the vitrified radioactive waste containers are stored, some of which only referenced 6 have been shown diagrammatically in FIG. 1.
  • the access shaft 2a is used to descend to the level of the galleries 3, the drums such as 7 from a loading machine 8 located on the surface having its own protection and movable on wheels.
  • a loading machine 8 located on the surface having its own protection and movable on wheels.
  • another transfer machine 9 takes up the drums 7 to route them along the gallery 3 and introduce them, as seen in the vertical well 5 on the left after removing the metal plate or plug 10 of this vertical well 5.
  • the base support 11 serving to support the column of drums 6 stacked in each well.
  • the ventilation by natural convection of the installation of FIG. 1 takes place as indicated by the arrows in the drawing, that is to say that the tube 2b is used for suction from the surface of the ground 1 of fresh air which then travels in the galleries 4 and, from there, in a hairpin along an ascending and descending path in each of the vertical wells 5 to be then evacuated in the form of hot air by axial ducts to each vertical storage well 5 and rise to the surface by the aeration well 2c.
  • it is the chimney effect which results from the presence in the vertical wells 5 of radioactive waste releasing a large amount of calories which allows this circulation of cooling air in the installation by natural convection.
  • the first upper plan 3 of galleries is located 500 meters deep. and the second plan 4 of galleries 30 meters below, that is to say 530 meters from the surface of the ground 1.
  • FIG. 2 there is shown schematically a plan view of the two levels of galleries 3 and 4 of the installation of Figure 1 above.
  • the level 3 galleries are shown in solid lines and the level 4 galleries in dashes to avoid any confusion.
  • This figure shows the access shafts 2a, the cooling air intake 2b and the hot air discharge 2c.
  • the total footprint of the installation in plan is 500 x 500 m, that is to say that each of the galleries of level 3, the total number of 17 distant from each other by 25 m, has a length of 500 m .
  • the galleries 4 of the lower plane are inclined at 45 ° to the galleries 3 of the upper plane and the different niches 12 containing the vertical storage wells 5 are arranged vertically in the galleries of the foreground horizontal 3 so as to allow the convenient loading of the wells 5.
  • These wells 5 are 149 on the whole surface, of which only a few are shown; they have a diameter of 3.2 m.
  • the galleries of levels 3 and 4 have a circular profile slightly flattened down and a diameter of 5 m.
  • the wells access or evacuation 2 have a diameter of 8 m.
  • two peripheral galleries 13 and 14 surround the oblique galleries of the lower level 4 and are intended, as will be described in more detail later, to facilitate the distribution of the cooling air coming from the surface and the hot air to be evacuated to the surface after it has passed through the vertical wells 5.
  • the 149 vertical storage wells 5 are located at the top of a square mesh network.
  • FIG 3 there is shown the detail of one of the niches 12 serving as support for a column of vitrified radioactive containers stacked in a vertical well such as 5.
  • this niche 12 we see a base support 11 in cast iron filled of concrete on which six housings 15, 16, 17, 18, 19 and 20 come to rest, at the bottom of which are anti-fall stools, not shown, which serve as support for the containers of vitrified waste which are housed there one above the other.
  • Each tube such as 20 is provided with a cold air inlet duct 21 which includes a baffle allowing the passage of this air while ensuring biological protection with respect to the radioactive products contained in the tube 20.
  • the six tubes for housing the stored products 15, 16, 17, 18, 19 and 20 are thus traversed by an ascending flow of fresh air which permanently licks the periphery of the vitrified containers stacked in each of the tubes.
  • An empty central tube 22 is assigned to the return of hot air from the upper part of the vertical well 5 to the hot air outlet pipe 23 which is connected to the exhaust gallery 14 of FIG. 2.
  • the well 5 has a height of 30 m and the tubes 15 to 20 contain 10 to 15 layers of six containers of vitrified radioactive waste each having a height of about 1.85 m.
  • Figure 5 shows in perspective one of the angles of the installation of vertical wells 5 between the galleries of the upper first plane 3 and the galleries of the second lower plane 4.
  • the hot air exhaust wells 2c and d cold air intake 2b as well as at the second level of the galleries 4 the belt of the two peripheral galleries 13 and 14 serving for the distribution and distribution of the fresh air arriving from the surface (solid lines) and the hot air exhausted to the surface (dashes).
  • a number of niches 12 are also visible in this figure as well as vertical wells 5 in exploded form making it possible to see the six peripheral storage tubes and the central hot air return tube.
  • a division into two compartments is carried out by a median plate 25 which separates the upper part of the pipe in which fresh air circulates from the lower part in which a second pipe 26 serves as a conduit conveying the hot air.
  • This plate 25 corresponds to the niche separation floor 12 such than the one seen at 24 in Figure 3.
  • the installation thus described with reference to the first five figures is suitable for receiving radioactive waste corresponding to the reprocessing of a plant processing 1600 tonnes of fuel per year and having operated for 30 years. It can thus definitively store around 24,000 drums of 220 liters each of vitrified radioactive waste without the temperature exceeding the critical value of 100 ° C on the surrounding rock. By way of clarification, it can be indicated that the peripheral evacuation gallery 14 of hot air does not exceed 90 ° C. in permanent operation.
  • FIG. 6 shows schematically and simplified a variant of the mode of circulation by natural convection of air in an installation of the same kind as that of the preceding figures.
  • the access shafts 2a, fresh air inlet 2b and hot air discharge 2c in connection with the galleries 3 of the foreground and the galleries 4 of the second lower plan.
  • the inclination of the galleries from one floor to the other has not been shown for simplicity.
  • the difference in design with the previous example here lies in the fact that the fresh air coming from the surface through the pipe 2b is injected directly into the galleries of level 4 and rises in one direction in all the wells 5 to lead in the various galleries of the foreground 3 and be evacuated overall by the pipe 2c from the upper foreground 3.
  • this variant therefore, there is no longer any natural circulation of air along a hairpin path in vertical storage wells 5.
  • Figures 7a, 7b, 7c and 7d show more several possible examples of the installation of vertical storage wells 5 in a regular network.
  • the galleries in the foreground 3 are shown in solid lines and, inclined at an angle ⁇ and in dashes, the galleries in the second plane 4 of the installation.
  • the purpose of these various figures is to show that the possible configurations of arrangement of the vertical storage wells 5 are quite numerous and in correspondence with the value of the angle a of inclination of the galleries of plane 3 on the galleries of plane 4.
  • the mesh of the storage wells 5 is a mesh in the form of a parallelogram and in the second case (FIG. 7d) it is a rectangular mesh.
  • reception rocks in which the galleries of the installation object of the invention are dug can be of very varied natures; we will nevertheless cite as particularly interesting the terrains made up of granite, clay, salt or volcanic rocks.

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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)
  • Processing Of Solid Wastes (AREA)
EP83400871A 1982-05-05 1983-04-29 Geologische Anlage zur Lagerung von radioaktivem Material, insbesondere in verglaster Form Expired EP0093671B1 (de)

Applications Claiming Priority (2)

Application Number Priority Date Filing Date Title
FR8207786A FR2526574A1 (fr) 1982-05-05 1982-05-05 Procede d'evacuation de dechets radioactifs et installation geologique pour l'evacuation de ces dechets
FR8207786 1982-05-05

Publications (2)

Publication Number Publication Date
EP0093671A1 true EP0093671A1 (de) 1983-11-09
EP0093671B1 EP0093671B1 (de) 1987-02-11

Family

ID=9273743

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EP83400871A Expired EP0093671B1 (de) 1982-05-05 1983-04-29 Geologische Anlage zur Lagerung von radioaktivem Material, insbesondere in verglaster Form

Country Status (5)

Country Link
US (1) US4500227A (de)
EP (1) EP0093671B1 (de)
JP (1) JPS5931499A (de)
DE (1) DE3369809D1 (de)
FR (1) FR2526574A1 (de)

Cited By (5)

* Cited by examiner, † Cited by third party
Publication number Priority date Publication date Assignee Title
EP0151035A3 (en) * 1984-02-01 1985-08-28 The English Electric Company Limited Storage arrangements for nuclear fuel
WO1997006536A1 (de) * 1995-08-09 1997-02-20 Nukem Gmbh Unterirdisches zwischenlager sowie verfahren zum zwischenlagern von abfall
RU2143758C1 (ru) * 1998-04-14 1999-12-27 Московское государственное предприятие - объединенный эколого-технологический и научно-исследовательский центр по обезвреживанию РАО и охране окружающей среды (МосНПО "Радон") Устройство для хранения радиоактивных и токсичных отходов
WO2008125803A1 (en) * 2007-04-12 2008-10-23 The University Of Sheffield Nuclear waste disposal
KR101279208B1 (ko) * 2005-09-16 2013-06-26 슈나이더 일렉트릭 인더스트리스 에스에이에스 모니터링 수단이 제공되는 전자 트립 디바이스, 그 트립디바이스를 포함하는 회로 차단기 및 모니터링 방법

Families Citing this family (16)

* Cited by examiner, † Cited by third party
Publication number Priority date Publication date Assignee Title
US4844839A (en) * 1984-09-04 1989-07-04 Manchak Frank In situ treatment and analysis of wastes
EP0193596A1 (de) * 1984-09-04 1986-09-10 MANCHAK, Frank Jr. Auf mülldeponien einsetzbare behandlungsvorrichtung und verfahren zu ihrer verwendung
US4776409A (en) * 1984-09-04 1988-10-11 Manchak Frank Insitu waste impoundment treating apparatus and method of using same
JPS61202198A (ja) * 1985-03-06 1986-09-06 清水建設株式会社 放射性廃棄物の岩盤内貯蔵設備
JPS61202199A (ja) * 1985-03-06 1986-09-06 清水建設株式会社 放射性廃棄物の岩盤内貯蔵設備
JPS61202200A (ja) * 1985-03-06 1986-09-06 清水建設株式会社 放射性廃棄物の岩盤内貯蔵設備
JPS61204599A (ja) * 1985-03-07 1986-09-10 清水建設株式会社 放射性廃棄物の岩盤内貯蔵設備
JPS63500677A (ja) * 1985-08-26 1988-03-10 マンチャック　フランク　ジュニア 危険廃棄物現場処理装置およびその使用方法
US5633508A (en) * 1995-10-12 1997-05-27 Cold Spring Granite Company Secondary shielding structure
US5850614A (en) * 1997-07-14 1998-12-15 Crichlow; Henry B. Method of disposing of nuclear waste in underground rock formations
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
RU2161830C2 (ru) * 1999-02-22 2001-01-10 Институт гидродинамики им. М.А. Лаврентьева СО РАН Способ импульсного пневматического транспортирования высокорадиоактивных отходов на захоронение и устройство для его осуществления
US6342650B1 (en) * 1999-06-23 2002-01-29 VALFELLS áGUST Disposal of radiation waste in glacial ice
JP3945225B2 (ja) * 2001-11-09 2007-07-18 鹿島建設株式会社 空気搬送システムによる地層処分方法
JP6495068B2 (ja) * 2015-03-30 2019-04-03 大成建設株式会社 管渠の構築方法および地下流路
US9833819B2 (en) 2015-04-06 2017-12-05 Safe Nuclear Solutions, LLC System for deep underground storage of radioactive waste

Citations (2)

* Cited by examiner, † Cited by third party
Publication number Priority date Publication date Assignee Title
DE2755554A1 (de) * 1976-12-13 1978-06-29 Tore Jerker Hallenius Einrichtung zum lagern radioaktiver materialien in felsigem untergrund
FR2411473A1 (fr) * 1977-12-06 1979-07-06 Strahlen Umweltforsch Gmbh Lieu de stockage final des dechets radioactifs

Family Cites Families (12)

* Cited by examiner, † Cited by third party
Publication number Priority date Publication date Assignee Title
US2788637A (en) * 1952-12-04 1957-04-16 Phillips Petroleum Co Underground storage systems and improved method of operating
SE390718B (sv) * 1975-05-28 1977-01-17 Abv Vegforbettringar Ab Anleggning for lagring av petroleumprodukter i underjordiska lagringsrum
US4020004A (en) * 1975-11-21 1977-04-26 The United States Of America As Represented By The United States Energy Research And Development Administration Conversion of radioactive ferrocyanide compounds to immobile glasses
US4040480A (en) * 1976-04-15 1977-08-09 Atlantic Richfield Company Storage of radioactive material
SE416690B (sv) * 1977-06-30 1981-01-26 Wp System Ab Anleggning for lagring av radioaktivt material i berg
US4192629A (en) * 1976-12-13 1980-03-11 Hallenius Tore J System for the storage of radioactive material in rock
GB2017797B (en) * 1978-02-21 1982-06-03 Sagefors K System for the storage of petroleum products and other fluids in a rock
US4230597A (en) * 1978-08-03 1980-10-28 Hittman Corporation Conversion of radioactive waste materials into solid form
US4326820A (en) * 1978-11-28 1982-04-27 Gesellschaft Fur Strahlen-Und Umweltforschung Mbh Munchen Final depository for radioactive wastes
US4320028A (en) * 1979-05-17 1982-03-16 Leuchtag H Richard Nuclear waste disposal system
US4269728A (en) * 1979-08-21 1981-05-26 The United States Of America As Represented By The United States Department Of Energy Method for storing spent nuclear fuel in repositories
FR2479542B1 (fr) * 1980-03-27 1987-08-07 Tech Nles Ste Gle Nouveaux materiaux barrieres utilisables pour le conditionnement des effluents radio-actifs

Patent Citations (2)

* Cited by examiner, † Cited by third party
Publication number Priority date Publication date Assignee Title
DE2755554A1 (de) * 1976-12-13 1978-06-29 Tore Jerker Hallenius Einrichtung zum lagern radioaktiver materialien in felsigem untergrund
FR2411473A1 (fr) * 1977-12-06 1979-07-06 Strahlen Umweltforsch Gmbh Lieu de stockage final des dechets radioactifs

Non-Patent Citations (1)

* Cited by examiner, † Cited by third party
Title
NUCLEAR ENERGY, vol. 21, no. 4, août 1982, pages 245-252, Londres, GB. *

Cited By (7)

* Cited by examiner, † Cited by third party
Publication number Priority date Publication date Assignee Title
EP0151035A3 (en) * 1984-02-01 1985-08-28 The English Electric Company Limited Storage arrangements for nuclear fuel
US4832903A (en) * 1984-02-01 1989-05-23 The English Electric Company Limited Dry storage arrangements for nuclear fuel
WO1997006536A1 (de) * 1995-08-09 1997-02-20 Nukem Gmbh Unterirdisches zwischenlager sowie verfahren zum zwischenlagern von abfall
US5920602A (en) * 1995-08-09 1999-07-06 Nukem Gmbh Underground storage facility, and associated method of storing waste
RU2143758C1 (ru) * 1998-04-14 1999-12-27 Московское государственное предприятие - объединенный эколого-технологический и научно-исследовательский центр по обезвреживанию РАО и охране окружающей среды (МосНПО "Радон") Устройство для хранения радиоактивных и токсичных отходов
KR101279208B1 (ko) * 2005-09-16 2013-06-26 슈나이더 일렉트릭 인더스트리스 에스에이에스 모니터링 수단이 제공되는 전자 트립 디바이스, 그 트립디바이스를 포함하는 회로 차단기 및 모니터링 방법
WO2008125803A1 (en) * 2007-04-12 2008-10-23 The University Of Sheffield Nuclear waste disposal

Also Published As

Publication number Publication date
US4500227A (en) 1985-02-19
DE3369809D1 (en) 1987-03-19
JPS5931499A (ja) 1984-02-20
FR2526574A1 (fr) 1983-11-10
JPH0340840B2 (de) 1991-06-20
FR2526574B1 (de) 1984-09-28
EP0093671B1 (de) 1987-02-11

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