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EP2550664B1 - Verfahren zur herstellung von gebinden zur lagerung von abfällen - Google Patents

Verfahren zur herstellung von gebinden zur lagerung von abfällen Download PDF

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Publication number
EP2550664B1
EP2550664B1 EP11711513.9A EP11711513A EP2550664B1 EP 2550664 B1 EP2550664 B1 EP 2550664B1 EP 11711513 A EP11711513 A EP 11711513A EP 2550664 B1 EP2550664 B1 EP 2550664B1
Authority
EP
European Patent Office
Prior art keywords
waste
graphite
matrix
glass
waste products
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
EP11711513.9A
Other languages
German (de)
English (en)
French (fr)
Other versions
EP2550664A1 (de
Inventor
Milan Hrovat
Richard Seemann
Karl-Heinz Grosse
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.)
ALD Vacuum Technologies GmbH
Original Assignee
ALD Vacuum Technologies GmbH
Priority date (The priority date 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 date listed.)
Filing date
Publication date
Application filed by ALD Vacuum Technologies GmbH filed Critical ALD Vacuum Technologies GmbH
Publication of EP2550664A1 publication Critical patent/EP2550664A1/de
Application granted granted Critical
Publication of EP2550664B1 publication Critical patent/EP2550664B1/de
Not-in-force legal-status Critical Current
Anticipated expiration legal-status Critical

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Classifications

    • GPHYSICS
    • G21NUCLEAR PHYSICS; NUCLEAR ENGINEERING
    • G21FPROTECTION AGAINST X-RADIATION, GAMMA RADIATION, CORPUSCULAR RADIATION OR PARTICLE BOMBARDMENT; TREATING RADIOACTIVELY CONTAMINATED MATERIAL; DECONTAMINATION ARRANGEMENTS THEREFOR
    • G21F9/00Treating radioactively contaminated material; Decontamination arrangements therefor
    • G21F9/28Treating solids
    • G21F9/34Disposal of solid waste
    • G21F9/36Disposal of solid waste by packaging; by baling
    • GPHYSICS
    • G21NUCLEAR PHYSICS; NUCLEAR ENGINEERING
    • G21FPROTECTION AGAINST X-RADIATION, GAMMA RADIATION, CORPUSCULAR RADIATION OR PARTICLE BOMBARDMENT; TREATING RADIOACTIVELY CONTAMINATED MATERIAL; DECONTAMINATION ARRANGEMENTS THEREFOR
    • G21F5/00Transportable or portable shielded containers
    • G21F5/005Containers for solid radioactive wastes, e.g. for ultimate disposal
    • GPHYSICS
    • G21NUCLEAR PHYSICS; NUCLEAR ENGINEERING
    • G21FPROTECTION AGAINST X-RADIATION, GAMMA RADIATION, CORPUSCULAR RADIATION OR PARTICLE BOMBARDMENT; TREATING RADIOACTIVELY CONTAMINATED MATERIAL; DECONTAMINATION ARRANGEMENTS THEREFOR
    • G21F9/00Treating radioactively contaminated material; Decontamination arrangements therefor
    • G21F9/04Treating liquids
    • G21F9/20Disposal of liquid waste
    • G21F9/22Disposal of liquid waste by storage in a tank or other container

Definitions

  • This invention relates to a process for producing a container for storing waste products.
  • the manufactured container is suitable for ultra-long, safe disposal and has a moisture-impermeable, corrosion-resistant graphite matrix and at least one Abfallkompartiment embedded in the matrix.
  • waste refers to any type of waste, preferably those that emit radioactive radiation or contain fission and decay products. This invention is particularly suitable for the disposal of high level waste (HLW) waste This includes, for example, waste generated during the reprocessing of spent fuel and, among other things, spent fuel that has not been reprocessed, is classified as HLW.
  • HLW high level waste
  • the process for producing HLW-containing glass blocks is most advanced.
  • the originating from the reprocessing plant CPR is preferably melted in borosilicate glass and the glass blocks produced are placed in stainless steel containers and thus represent the waste package (Waste Package).
  • the outer steel containers represent both the corrosion protection layer and the diffusion barrier for radionuclides.
  • the corrosion resistance of the containers depends above all on the container type, the presence of moisture and the associated radiolysis at temperatures above 100 ° C.
  • the steel containers according to the prior art have the object, both the corrosion of the steel container and the diffusion of radionuclides from the HLW-containing components such. Glass blocks to prevent.
  • a matrix material which comprises graphite and an inorganic binder and is suitable for disposal of radioactive waste.
  • inorganic binders glasses aluminosilicates, silicates, borates and / or lead sulfides are provided.
  • Powdered radioactive waste is embedded in the matrix by directly mixing the waste with the matrix components.
  • Waste in the form of geometric bodies is embedded by filling the waste in cavities of a molded body produced from the matrix components.
  • the containers made by the process of the invention comprise a matrix and waste compartments embedded in the matrix.
  • the waste compartments preferably include waste containing composite pressed elements (e.g., bars) that are seamlessly enclosed by a metallic shell.
  • the waste compartments have waste products in a metal shell.
  • the waste products may be mixed with a binder, which is preferably also glass.
  • the matrix comprises graphite and glass as an inorganic binder.
  • the waste products may in particular also be spent fuel assemblies.
  • waste products are mentioned in this specification, it is meant that wastes are usually mixtures of several products, but according to the invention this term also includes products which consist only of a single component.
  • the manufactured container is characterized by an inverse design.
  • the waste compartments are embedded in the corrosion-resistant, impermeable graphite glass matrix (IGG matrix) in the method according to the invention. It is essential that the function of an outer steel container is displaced by the metal envelope of the waste products in the inner container area, therefore "inverse design".
  • Graphite is known to be a material that has a high corrosion stability and radiation stability. This has already been confirmed by natural graphite, which has been present in nature for millions of years in unaltered form.
  • the graphite content of the matrix is preferably 60 to 90 wt .-%. It is preferable the graphite is natural graphite or synthetic graphite or a mixture of both components. It is particularly preferred that the graphite content in the matrix material to 60 wt .-% to 100 wt .-% of natural graphite and 0 wt .-% to 40 wt .-% consists of synthetic graphite.
  • the synthetic graphite may also be referred to as graphitized electrographite powder.
  • the natural graphite has the advantage that it is inexpensive, the graphite grain in contrast to synthetic graphite has no nanorises and can be pressed at moderate pressure to give moldings with almost theoretical density.
  • the glass used as binder in the process according to the invention is preferably borosilicate glass.
  • the advantage of borosilicate glasses is their high corrosion stability. Borosilicate glasses are very chemical and temperature resistant glasses. The good chemical resistance, for example to water and many chemicals is explained by the boron content of the glasses. The temperature resistance and insensitivity of the borosilicate glasses against sudden temperature fluctuations are due to their low coefficient of thermal expansion of about 3.3x10 -6 K -1 . Common borosilicate glasses include Duran®, Pyrex®, Ilmabon®, Simax® Solidex® and Fiolax®.
  • the binders according to the method of the invention also have the advantage that during the heat treatment they do not form gaseous cracking products which lead to pore formation in the matrix. This means that the inorganic binders do not undergo any conversion processes and thus no pores are formed.
  • the glass used has the advantage that it seals pores that can still form, resulting in said high density, impermeability to moisture and excellent corrosion resistance.
  • the glass in a proportion of up to 40% by weight in the matrix. More preferably, the glass is present in a proportion of 10 to 30 wt .-% and more preferably in a proportion of 15 to 25 wt .-% in the matrix.
  • the produced Matrix substantially free of pores, namely, it has a density which is preferably in the range of> 99% of the theoretical density. It is important that the graphite matrix has a high density so that no moisture can penetrate into the produced container. This is ensured on the one hand by the selection of materials and on the other hand by the production process according to the invention.
  • the dissipation heat of the radionuclides is significantly improved due to the high thermal conductivity of the IGG matrix.
  • the waste products can basically have any conceivable shape.
  • the waste products are preferably cylindrical. This is particularly true when the container produced has the preferred shape of a hexagonal prism.
  • the containers produced preferably have a key width of 400 to 600 mm and a preferred height of 800 to 1200 mm.
  • waste compartments can be arranged in the form of rods in a trigonal 8-row design.
  • absorber rods For neutron absorption, a part of it (5-10%) can be covered with absorber rods.
  • absorber material B 4 C can be used.
  • the IGG matrix can be prepared by mixing the starting components in powder form.
  • the molding powder is preferably prepared by mixing graphite powder with glass powder.
  • the press powder may comprise adjuvants in amounts of a few percent, based on the total amount. These are, for example, pressing aids which may comprise alcohols.
  • the graphite powder is preferably used with a particle diameter of ⁇ 30 .mu.m.
  • the remaining components preferably have about the same grain size as the graphite powder.
  • a granulate is produced from the pressed powder.
  • the starting components in particular the two components graphite and glass powder, mixed together, then compacted and then breaking and sieving granules are made with a grain size of less than 3.14 mm and greater than 0.31 mm.
  • a handle-resistant base body is pre-pressed with recesses for receiving metal-coated waste, such as waste-containing composite-pressed rods or columns.
  • the pre-pressing takes place, for example, with a four-column press with three hydraulic drives.
  • the press die stands freely on the lower yoke of the press and is only positioned by a centering stop.
  • shaped rods which are composed of two parts preferably serve to produce recesses:
  • a shaping rod part with a larger diameter which is placed on a thinner support rod.
  • a lower punch is raised so far that up to a Matrizenobercons the required filling space is created.
  • a pre-dosed granule portion is filled evenly, first pre-compacted with the upper punch and then together with unlocked lower punch with the upper punch pushed down so far that the Matrizenobercons again the same filling space. This process is repeated until the required length of the compact is reached. Since the pressure required for pushing is always below the pressing pressure, it is possible to produce the pre-pressed basic body over the entire length in a density-free manner. This is an important prerequisite for avoiding bending of the waste compartments during final pressing.
  • both production steps, granule production and pre-pressing of the base body are carried out outside of hot cells (remote operation).
  • waste-containing CPR-compressed waste compartments takes place in hot cells.
  • metal sheaths preferably made of copper
  • a preferably homogeneous mixture of radioactive waste and glass as a binder. After closing the loaded casings, they are heated in an extruder and extruded into composite-pressed waste compartments.
  • Such a modified method is also suitable for the production of waste packages spent and unprocessed fuel rods from, for example, LWR and SWR (light water and heavy water reactors).
  • the rods of the LWR have a length of up to 4800 mm, they are first pushed into copper tubes, then formed into spiral bodies and finally embedded in layers in the graphite-glass matrix.
  • the modified method is also suitable for the safe disposal of irradiated and radioisotope contaminated graphite from graphite-moderated nuclear power plants, such as e.g. Magnox or AGR from UK, UNGG from France and RBMK from Russia.
  • the waste package is based on the Dragon 18-pin BE design for high-temperature reactors.
  • the container is preferably a hexagonal prism with a key width of 500 mm and a height of 1000 mm.
  • according to the invention is preferably a low-melting borosilicate glass as a binder and for the metal sheaths (cylinder) instead of copper preferably an aluminum-magnesium alloy used in particular AIMg1. Since decay heat is negligible compared to highly radioactive waste, the diameter of the recesses for the irradiated graphite (IG) loaded cylinder is increased to 80 mm diameter. Thus, about 120 kg of irradiated graphite can be embedded in the waste package.
  • IG irradiated graphite
  • the waste products are introduced in a mixture with glass in the metal shell.
  • the compaction of the waste products is preferably carried out by pressing.
  • Preferred densification processes include, in addition to extrusion and hot isostatic pressing (HIP), forging.
  • the manufactured container is a prism of IGG matrix, which contains in the inner area the copper-clad, composite-pressed waste compartments in the form of rods.
  • the starting components used were a nuclear grade natural graphite having a particle diameter of less than 30 ⁇ m from Kropfmühl and a borosilicate glass of the same particle size having a melting point of about 1000 ° C. from Schott.
  • the two components were mixed dry in a weight ratio of natural graphite to glass 5: 1 and pressed into briquettes with the compactor Bepex L 200/50 P from Hosokawa.
  • the briquette density was about 1.9 g / cm 3 .
  • a granule having a grain size of less than 3.14 mm and greater than 0.31 mm and having a bulk density of about 1 g / cm 3 was prepared.
  • the pre-pressing was carried out in several successive layers.
  • the shaped rods had a diameter larger by 0.2 mm than the support rods.
  • the pressing pressure was 40 MN / m 2 and the sliding pressure was less than 20 MN / m 2 in the entire compact structure.
  • the copper cylinders were loaded with a homogeneous mixture of CPR simulant in borosilicate powder. After sealing, the cylinders were heated to 1000 ° C in a strand press and extruded into composite pressed bars at a throat factor of 3. In this case, a density of about 90% of the theoretical density, based on the waste, was achieved in the bars.
  • the base body After assembling the base body with the composite-pressed waste rods, it was heated to 1000 ° C and finish-pressed.
  • the final pressing is a dynamic pressing.
  • the compact was moved under full load alternately with the upper and lower punches in the die. After cooling to 200 ° C. the pellet was ejected from the tool.
  • fuel rod dummies dummy fuel rods
  • tubular metal casings of copper with a gap width of about 1 mm.
  • the final pressing of the waste packages is described in Example 1.
  • Example 2 Analogous to Example 1, the base body with 19 recesses of 81 mm diameter was produced from the graphite glass granules. Subsequently, the hollow cylinders made of AIMg1 alloy were loaded with a homogeneous mixture of glass and IG graphite. After loading, the cylinders were sealed and made by extrusion at 500 ° C into 80 mm diameter columns. In this case, a density in the columns, based on the IG graphite in the matrix, of 1.75 g / cm 3 was achieved. After assembling the base body, it was finish-pressed analogously to Example 1.

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  • Engineering & Computer Science (AREA)
  • Physics & Mathematics (AREA)
  • General Engineering & Computer Science (AREA)
  • High Energy & Nuclear Physics (AREA)
  • Environmental & Geological Engineering (AREA)
  • Processing Of Solid Wastes (AREA)
EP11711513.9A 2010-03-25 2011-03-24 Verfahren zur herstellung von gebinden zur lagerung von abfällen Not-in-force EP2550664B1 (de)

Applications Claiming Priority (2)

Application Number Priority Date Filing Date Title
DE102010003289.1A DE102010003289B4 (de) 2010-03-25 2010-03-25 Gebinde zur Lagerung von radioaktiven Abfällen und Verfahren zu seiner Herstellung
PCT/EP2011/054549 WO2011117354A1 (de) 2010-03-25 2011-03-24 Gebinde zur lagerung von abfällen

Publications (2)

Publication Number Publication Date
EP2550664A1 EP2550664A1 (de) 2013-01-30
EP2550664B1 true EP2550664B1 (de) 2013-12-25

Family

ID=44279809

Family Applications (1)

Application Number Title Priority Date Filing Date
EP11711513.9A Not-in-force EP2550664B1 (de) 2010-03-25 2011-03-24 Verfahren zur herstellung von gebinden zur lagerung von abfällen

Country Status (12)

Country Link
US (1) US20130012374A1 (ru)
EP (1) EP2550664B1 (ru)
JP (1) JP5313412B2 (ru)
KR (1) KR101450016B1 (ru)
CN (1) CN102906822A (ru)
BR (1) BR112012024304A2 (ru)
CA (1) CA2794405C (ru)
DE (1) DE102010003289B4 (ru)
EA (1) EA023726B1 (ru)
ES (1) ES2454565T3 (ru)
UA (1) UA105288C2 (ru)
WO (1) WO2011117354A1 (ru)

Families Citing this family (8)

* Cited by examiner, † Cited by third party
Publication number Priority date Publication date Assignee Title
DE102012101165A1 (de) 2012-02-14 2013-08-14 Ald Vacuum Technologies Gmbh Dekontaminationsverfahren für radioaktiv kontaminiertes Material
DE102012101161A1 (de) 2012-02-14 2013-08-14 Ald Vacuum Technologies Gmbh Abtrennung von Radionukliden aus kontaminiertem Material
DE102012112642A1 (de) * 2012-12-19 2014-06-26 Ald Vacuum Technologies Gmbh Graphitmatrix mit Glaskeramik als Bindemittel
DE102012112648B4 (de) * 2012-12-19 2016-08-04 Ald Vacuum Technologies Gmbh Graphitmatrix mit kristallinem Bindemittel
FR3001958B1 (fr) * 2013-02-13 2016-02-05 Andra Procede et casier d'entreposage de colis de substances radioactives dans un puits
DE102014110168B3 (de) * 2014-07-18 2015-09-24 Ald Vacuum Technologies Gmbh Verfahren zur Dekontamination von kontaminiertem Graphit
CN106098131B (zh) * 2016-07-17 2018-05-01 福建省德鲁士润滑油有限公司 一种核废料包装装置
EP4148162A1 (de) 2021-09-13 2023-03-15 Behzad Sahabi Beschichtungsverfahren und vorrichtung zum ausbilden einer barriereschicht zur erhöhung der impermeabilität und korrosionsbeständigkeit, beschichtung und gebinde zur einbettung und versiegelung radioaktiver körper für die endlagerung, sowie verfahren zur herstellung des gebindes

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WO2010052321A1 (de) * 2008-11-10 2010-05-14 Ald Vacuum Technologies Gmbh Matrixmaterial aus graphit und anorganischen bindemitteln geeignet zur endlagerung von radioaktiven abfällen, verfahren zu dessen herstellung, dessen verarbeitung und verwendung

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Also Published As

Publication number Publication date
KR20120125670A (ko) 2012-11-16
ES2454565T3 (es) 2014-04-10
JP5313412B2 (ja) 2013-10-09
DE102010003289A1 (de) 2011-09-29
CN102906822A (zh) 2013-01-30
BR112012024304A2 (pt) 2019-09-24
WO2011117354A1 (de) 2011-09-29
CA2794405C (en) 2014-02-04
EA201201328A1 (ru) 2013-03-29
CA2794405A1 (en) 2011-09-29
EA023726B1 (ru) 2016-07-29
KR101450016B1 (ko) 2014-10-15
EP2550664A1 (de) 2013-01-30
UA105288C2 (ru) 2014-04-25
US20130012374A1 (en) 2013-01-10
JP2013524165A (ja) 2013-06-17
DE102010003289B4 (de) 2017-08-24

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