EP1999759A2 - Method and apparatus for final storage and safe operation of nuclear power stations - Google Patents
Method and apparatus for final storage and safe operation of nuclear power stationsInfo
- Publication number
- EP1999759A2 EP1999759A2 EP07723561A EP07723561A EP1999759A2 EP 1999759 A2 EP1999759 A2 EP 1999759A2 EP 07723561 A EP07723561 A EP 07723561A EP 07723561 A EP07723561 A EP 07723561A EP 1999759 A2 EP1999759 A2 EP 1999759A2
- Authority
- EP
- European Patent Office
- Prior art keywords
- shaft
- repository
- wellbore
- section
- rock
- 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
Links
- 238000000034 method Methods 0.000 title claims abstract description 55
- 238000003860 storage Methods 0.000 title claims description 11
- 229910052751 metal Inorganic materials 0.000 claims abstract description 56
- 239000002184 metal Substances 0.000 claims abstract description 56
- 239000011435 rock Substances 0.000 claims abstract description 43
- 239000000463 material Substances 0.000 claims abstract description 33
- 238000005553 drilling Methods 0.000 claims abstract description 30
- 239000012857 radioactive material Substances 0.000 claims abstract description 27
- 230000002285 radioactive effect Effects 0.000 claims abstract description 13
- OKTJSMMVPCPJKN-UHFFFAOYSA-N Carbon Chemical compound [C] OKTJSMMVPCPJKN-UHFFFAOYSA-N 0.000 claims abstract description 12
- 239000007788 liquid Substances 0.000 claims abstract description 12
- 230000015572 biosynthetic process Effects 0.000 claims abstract description 11
- 230000005484 gravity Effects 0.000 claims abstract description 11
- 239000012530 fluid Substances 0.000 claims abstract description 10
- 238000004519 manufacturing process Methods 0.000 claims abstract description 9
- 238000012432 intermediate storage Methods 0.000 claims abstract description 8
- 239000000155 melt Substances 0.000 claims abstract description 6
- 230000000694 effects Effects 0.000 claims abstract description 5
- 238000005260 corrosion Methods 0.000 claims abstract 2
- 230000007797 corrosion Effects 0.000 claims abstract 2
- 238000010438 heat treatment Methods 0.000 claims abstract 2
- 238000002347 injection Methods 0.000 claims abstract 2
- 239000007924 injection Substances 0.000 claims abstract 2
- 125000006850 spacer group Chemical group 0.000 claims abstract 2
- 229910002804 graphite Inorganic materials 0.000 claims description 10
- 239000010439 graphite Substances 0.000 claims description 10
- 238000002844 melting Methods 0.000 claims description 9
- 230000008569 process Effects 0.000 claims description 9
- 230000008018 melting Effects 0.000 claims description 8
- 230000007423 decrease Effects 0.000 claims description 3
- 239000000446 fuel Substances 0.000 claims description 3
- XLYOFNOQVPJJNP-UHFFFAOYSA-N water Substances O XLYOFNOQVPJJNP-UHFFFAOYSA-N 0.000 claims description 3
- 239000003673 groundwater Substances 0.000 claims description 2
- 230000020169 heat generation Effects 0.000 claims description 2
- 231100000331 toxic Toxicity 0.000 claims description 2
- 230000002588 toxic effect Effects 0.000 claims description 2
- 239000002915 spent fuel radioactive waste Substances 0.000 claims 4
- 239000002826 coolant Substances 0.000 claims 1
- 238000009751 slip forming Methods 0.000 claims 1
- 239000002699 waste material Substances 0.000 abstract description 7
- 238000005025 nuclear technology Methods 0.000 abstract description 2
- 238000005538 encapsulation Methods 0.000 abstract 8
- 229910052799 carbon Inorganic materials 0.000 abstract 2
- 238000013508 migration Methods 0.000 abstract 2
- 230000005012 migration Effects 0.000 abstract 2
- 239000002901 radioactive waste Substances 0.000 abstract 2
- 239000000969 carrier Substances 0.000 abstract 1
- 239000013529 heat transfer fluid Substances 0.000 abstract 1
- 239000003758 nuclear fuel Substances 0.000 abstract 1
- 238000007789 sealing Methods 0.000 abstract 1
- 230000032258 transport Effects 0.000 description 14
- 238000010276 construction Methods 0.000 description 10
- 239000002609 medium Substances 0.000 description 7
- 238000000926 separation method Methods 0.000 description 4
- 230000008901 benefit Effects 0.000 description 3
- 238000005755 formation reaction Methods 0.000 description 3
- 238000009434 installation Methods 0.000 description 3
- 230000005855 radiation Effects 0.000 description 3
- 150000003839 salts Chemical class 0.000 description 3
- 239000007787 solid Substances 0.000 description 3
- 229910001018 Cast iron Inorganic materials 0.000 description 2
- 238000005275 alloying Methods 0.000 description 2
- 238000005516 engineering process Methods 0.000 description 2
- 229910001385 heavy metal Inorganic materials 0.000 description 2
- 230000007774 longterm Effects 0.000 description 2
- 239000000941 radioactive substance Substances 0.000 description 2
- 230000009467 reduction Effects 0.000 description 2
- PEDCQBHIVMGVHV-UHFFFAOYSA-N Glycerine Chemical compound OCC(O)CO PEDCQBHIVMGVHV-UHFFFAOYSA-N 0.000 description 1
- 230000001133 acceleration Effects 0.000 description 1
- 238000009825 accumulation Methods 0.000 description 1
- 239000011149 active material Substances 0.000 description 1
- 238000007664 blowing Methods 0.000 description 1
- 229910021538 borax Inorganic materials 0.000 description 1
- 238000009933 burial Methods 0.000 description 1
- 239000013078 crystal Substances 0.000 description 1
- 230000008021 deposition Effects 0.000 description 1
- 238000004512 die casting Methods 0.000 description 1
- 238000009826 distribution Methods 0.000 description 1
- 230000007613 environmental effect Effects 0.000 description 1
- 231100000518 lethal Toxicity 0.000 description 1
- 230000001665 lethal effect Effects 0.000 description 1
- 238000005065 mining Methods 0.000 description 1
- 239000000203 mixture Substances 0.000 description 1
- 230000035699 permeability Effects 0.000 description 1
- 239000004328 sodium tetraborate Substances 0.000 description 1
- 235000010339 sodium tetraborate Nutrition 0.000 description 1
- 239000002352 surface water Substances 0.000 description 1
- 239000006163 transport media Substances 0.000 description 1
- 239000003643 water by type Substances 0.000 description 1
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
Definitions
- the invention relates to a method for creating a secure repository in a well bore created by melt drilling, which has a solidified melt borehole casing, in particular a metallic Borlochverschalung.
- the invention further relates to a device for creating secure repository comprising at least one wellbore with a Borlochverschalung, in particular 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 up to Drilling target and in particular at depths up to 20 km or even more is known, for example, from the publication EP 1 157 187 B1 of the same Applicant, the content of which is fully incorporated herein by reference.
- 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.
- 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 ,
- 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.
- more conduit elements can be attached to the previous element to continuously drill the hole.
- 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 it can also be used other methods, if this suitable to create a borehole casing, in particular from a cast.
- 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.
- 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 runs until 2010 at the latest and is to 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.
- the invention has for its object to overcome these disadvantages and to meet the demand for a .best réelle repository 1 .
- 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.
- the object is further achieved in that in a repository at least one lower hole section (1/7) of a interconnected well after separation of repository material, especially in the subcritical state, is separated / separated from the rest of the wellbore to self-heat generation and / or rock pressure and / or self-weight under gravity and / or molten rock formation to sink towards the center of the earth.
- the molten metal drilling method according to EP 1 157 187 B1 offers a technically feasible drilling method with which, in a continuous melt-drilling process, production-ready superfinishes can be produced quickly and inexpensively.
- Deep wells with a large, well-defined drill hole diameter can be created to depths of 20 km or more.
- a seamless die-cast well casing is simultaneously created from acting as a drilling medium molten metal, which serves the magnetic slider as .Re hopessschiene '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.
- 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.
- 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 wellbin section / repository segment is preferred, when the outer contour is designed to be conically widened downwards, whereby the enormous lateral pressure forces to vertical thrust force.
- This erfindunstraunstrae 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 shroud / plutonic rock, especially since these fluids under the prevailing temperature and pressure conditions can be supercritical and therefore their friction value drastically reduced.
- 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.
- At least one wellbore for example, a 20 km deep wellbore (10) is drilled by the described molten metal drilling method.
- An upper, larger section for example more than three quarters of the borehole shaft thus created, in particular with a diameter that is constant throughout, for example of preferably more than 0.5 meters, is provided with a borehole casing,
- a borehole casing In particular, thick-walled metal casing of a cast and preferably good magnetic permeability provided, and can be used according to the invention as a repository shaft to bring material to be stored in a lower, smaller section, for example, less than a quarter of the wellbore.
- the lower wellbore portion particularly the lower quarter or less than a final disposal segment (1) e.g. be used for high-level 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.
- 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.
- the lower section used as the repository segment (1) in the production of the wellbore (10) in the region of the cast metal casing can be designed such that the wall thickness in the lower region is greater than in the upper region, for example starting at 0.25 m and above 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 a wellbill section directly above the final storage, eg filled with highly radioactive material and preferably with example liquid lead encapsulated Endlagersegments (1) can be preferably carried out so that at the same time for safe closure of the separated Endlagersegments (1) by the resulting molten metal, which are above the Endlagersegmentes settles and can form a metal lid closure (5) and / or floats directly on the liquid lead and forms a solid metal closure with the remainder of the Endlagersegmentverschalung.
- the remaining shuttering-free Abschmelz Scheme (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.
- a material eg Borax
- 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 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.
- 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, whereby 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 reactor new buildings and thus be optimally designed.
- 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 can be lined and if necessary, in addition with special crucible made of graphite so is designed so that the inflowing reactor melt can be distributed in the available graphite crucible and can be promoted after a cooldown on the automated transport system to the repository.
- 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.
- 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.
- 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.
- 5 x 1000 m repository segments with a repository volume of about 5000 m 3 can be used per deep well.
- 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.
- Repository material e.g., high level radioactive / heat evolving
- Moderator and / or heat transport medium e.g., liquid lead
- Transport tunnels for example, connecting tunnel reactor interim storage repository
Landscapes
- 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)
- Processing Of Solid Wastes (AREA)
- Underground Structures, Protecting, Testing And Restoring Foundations (AREA)
- Structure Of Emergency Protection For Nuclear Reactors (AREA)
- Catching Or Destruction (AREA)
Abstract
Description
Claims
Applications Claiming Priority (2)
| Application Number | Priority Date | Filing Date | Title |
|---|---|---|---|
| DE102006013836A DE102006013836A1 (en) | 2006-03-24 | 2006-03-24 | Creating final geological repository in base region of super-deep bore shaft by magnetically glided, directional melt drilling for disposing highly radioactive waste materials, comprises subcritically disposing the materials into the shaft |
| PCT/EP2007/002613 WO2007110211A2 (en) | 2006-03-24 | 2007-03-23 | Method and apparatus for final storage and safe operation of nuclear power stations |
Publications (2)
| Publication Number | Publication Date |
|---|---|
| EP1999759A2 true EP1999759A2 (en) | 2008-12-10 |
| EP1999759B1 EP1999759B1 (en) | 2010-08-25 |
Family
ID=38438415
Family Applications (1)
| Application Number | Title | Priority Date | Filing Date |
|---|---|---|---|
| EP07723561A Not-in-force EP1999759B1 (en) | 2006-03-24 | 2007-03-23 | Method and apparatus for final storage and safe operation of nuclear power stations |
Country Status (5)
| Country | Link |
|---|---|
| US (1) | US8693609B2 (en) |
| EP (1) | EP1999759B1 (en) |
| AT (1) | ATE479190T1 (en) |
| DE (2) | DE102006013836A1 (en) |
| WO (1) | WO2007110211A2 (en) |
Cited By (1)
| Publication number | Priority date | Publication date | Assignee | Title |
|---|---|---|---|---|
| RU2431210C1 (en) * | 2010-04-26 | 2011-10-10 | Открытое акционерное общество "Восточно-Европейский головной научно-исследовательский и проектный институт энергетических технологий" (ОАО "Головной институт "ВНИПИЭТ") | Underground long-term storage and/or deposition facility for packings of radioactive wastes |
Families Citing this family (9)
| Publication number | Priority date | Publication date | Assignee | Title |
|---|---|---|---|---|
| SE532961C2 (en) * | 2008-02-21 | 2010-05-25 | Oyster Internat Nv | Procedure for storing hazardous materials |
| DE102008049943A1 (en) * | 2008-10-02 | 2010-04-08 | Werner Foppe | Method and device for melt drilling |
| RU2550092C2 (en) * | 2013-07-31 | 2015-05-10 | Открытое Акционерное Общество "Акмэ-Инжиниринг" | Method for prolonged storage of spent nuclear fuel |
| US10115489B2 (en) | 2016-09-12 | 2018-10-30 | Grand Abyss, Llc | Emergency method and system for in-situ disposal and containment of nuclear material at nuclear power facility |
| US10115490B1 (en) | 2017-04-06 | 2018-10-30 | Mwd-Ip Holdings, Llc | Method for nuclear waste storage and monitoring |
| CZ308559B6 (en) * | 2019-05-31 | 2020-11-25 | Ăšstav struktury a mechaniky hornin AV ÄŚR, v.v.i. | Container for deep storage of spent nuclear fuel and method of deep storage of spent nuclear fuel with this container |
| US20220367080A1 (en) * | 2019-10-07 | 2022-11-17 | Deep Isolation, Inc. | Storing hazardous waste material |
| US12162051B2 (en) | 2021-04-28 | 2024-12-10 | Henry Crichlow | Disposal of high-level waste into deep salt formations |
| CN114278218B (en) * | 2021-12-15 | 2022-08-09 | 吉林大学 | Polar region grain snow layer vertical drilling hot melting drill bit based on liquid metal |
Family Cites Families (9)
| Publication number | Priority date | Publication date | Assignee | Title |
|---|---|---|---|---|
| US3357505A (en) * | 1965-06-30 | 1967-12-12 | Dale E Armstrong | High temperature rock drill |
| DE3001348A1 (en) * | 1980-01-16 | 1981-07-23 | Max 2120 Lüneburg Jahns | Atomic waste stored below earth crust - in layer remote from influence zone of earthquakes |
| CA2005376C (en) * | 1989-12-13 | 1996-11-19 | James Russell Baird | Subductive waste disposal method |
| DE3914617A1 (en) * | 1989-05-03 | 1990-11-08 | Werner Foppe | DEVICES AND METHODS FOR THE WARRANTY OF CONTINUOUSLY PROCESSING MELT DRILLING PROCESSES FOR DEEP HOLES |
| DE19500024A1 (en) * | 1995-01-02 | 1996-07-04 | Foppe Werner | Microwave-superheated, steam plasma jet melt-boring of rock, consuming only electrical energy and water |
| DE19528496C1 (en) * | 1995-05-03 | 1996-10-24 | Thomas Samland | Final disposal of radioactive material in deep borehole in tectonic valley |
| DE19721188A1 (en) * | 1997-05-21 | 1999-05-12 | Martin Hauck | Final nuclear waste storage |
| DE19909836A1 (en) * | 1999-03-05 | 2000-09-07 | Werner Foppe | Molten metal drilling process |
| JP2005091059A (en) * | 2003-09-16 | 2005-04-07 | Hiroshi Kawai | Method of disposal just under original place of power plant installation |
-
2006
- 2006-03-24 DE DE102006013836A patent/DE102006013836A1/en not_active Withdrawn
-
2007
- 2007-03-23 WO PCT/EP2007/002613 patent/WO2007110211A2/en not_active Ceased
- 2007-03-23 US US12/294,260 patent/US8693609B2/en not_active Expired - Fee Related
- 2007-03-23 DE DE502007004859T patent/DE502007004859D1/en active Active
- 2007-03-23 EP EP07723561A patent/EP1999759B1/en not_active Not-in-force
- 2007-03-23 AT AT07723561T patent/ATE479190T1/en active
Non-Patent Citations (1)
| Title |
|---|
| See references of WO2007110211A3 * |
Cited By (1)
| Publication number | Priority date | Publication date | Assignee | Title |
|---|---|---|---|---|
| RU2431210C1 (en) * | 2010-04-26 | 2011-10-10 | Открытое акционерное общество "Восточно-Европейский головной научно-исследовательский и проектный институт энергетических технологий" (ОАО "Головной институт "ВНИПИЭТ") | Underground long-term storage and/or deposition facility for packings of radioactive wastes |
Also Published As
| Publication number | Publication date |
|---|---|
| EP1999759B1 (en) | 2010-08-25 |
| DE102006013836A1 (en) | 2007-09-27 |
| WO2007110211A3 (en) | 2009-02-19 |
| US8693609B2 (en) | 2014-04-08 |
| WO2007110211A2 (en) | 2007-10-04 |
| ATE479190T1 (en) | 2010-09-15 |
| DE502007004859D1 (en) | 2010-10-07 |
| US20090145659A1 (en) | 2009-06-11 |
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