EP2550664A1 - Colis pour le stockage de déchets - Google Patents

Colis pour le stockage de déchets

Info

Publication number
EP2550664A1
EP2550664A1 EP11711513A EP11711513A EP2550664A1 EP 2550664 A1 EP2550664 A1 EP 2550664A1 EP 11711513 A EP11711513 A EP 11711513A EP 11711513 A EP11711513 A EP 11711513A EP 2550664 A1 EP2550664 A1 EP 2550664A1
Authority
EP
European Patent Office
Prior art keywords
waste
container
matrix
glass
graphite
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
EP11711513A
Other languages
German (de)
English (en)
Other versions
EP2550664B1 (fr
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/fr
Application granted granted Critical
Publication of EP2550664B1 publication Critical patent/EP2550664B1/fr
Not-in-force legal-status Critical Current
Anticipated expiration legal-status Critical

Links

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
    • G21F9/28—Treating solids
    • G21F9/34—Disposal of solid waste
    • G21F9/36—Disposal of solid waste by packaging; by baling
    • 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
    • G21F5/00—Transportable or portable shielded containers
    • G21F5/005—Containers for solid radioactive wastes, e.g. for ultimate disposal
    • 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
    • G21F9/22—Disposal of liquid waste by storage in a tank or other container

Definitions

  • waste refers to any type of waste, preferably one that emits radioactive radiation or that contains fission and decay products.
  • This invention is particularly suitable for the disposal of high level waste (HLW) 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
  • wastes are in liquid form after work-up and are usually converted by calcination into a solid form.
  • decay heat and half-life of the individual radionuclides differ from one another by several powers of ten.
  • 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).
  • Container production have an expected corrosion resistance of about 10,000 years. Consequently, safe containment of radioactive waste beyond this period is not guaranteed. In addition, the removal of the decay heat from the known containers is difficult because of low thermal conductivity.
  • Fluidized bed plants associated with a high demand for carrier gases (up to 20 m 3 / h), followed by the difficult and complex conditioning of the particles. Added to this is the expensive disposal of the carrier gas.
  • the containers 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 thus preferably 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.
  • wastes are usually mixtures of several products, but according to the invention this term also includes products which consist of only a single component.
  • the container is characterized by an inverse design.
  • the outside with a Enclosed steel containers are in the waste packages according to the invention, the waste compartments in the corrosion-resistant, moisture-impermeable
  • IGF matrix embedded (impermeable) graphite glass matrix
  • the requirement to both prevent corrosion and to avoid the diffusion of radionuclides is fulfilled separately in the containers according to the invention.
  • the IGG matrix is preferably as free of pores as possible and has a high density, which is close to the theoretical density, and is therefore impermeable to moisture and corrosion.
  • the inner metal cladding acts as a diffusion barrier.
  • 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 preferred that 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 according to the invention 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 Eiektrographitpulver.
  • the natural graphite has the advantage that it is inexpensive, the graphite grain, in contrast to synthetic graphite has no nanorises and moderate pressure to Moldings can be pressed with almost theoretical density.
  • the glass used as a binder in this invention is preferably borosilicate glass.
  • the advantage of Borosiükatgläsern is their high corrosion resistance.
  • Borosilicate glasses are very chemical and temperature resistant glasses. The good chemical resistance, for example to water and many chemicals is explained by the
  • Borosilicate glasses against sudden temperature fluctuations are the result of their low coefficient of thermal expansion of about 3.3x1 O.K "1.
  • Common borosilicate glasses include Duran®, Pyrex®, llmabon®, Simax® Solidex® and Fiolax®
  • the inorganic binder in a proportion of up to 40% by weight in the matrix. More preferably, the inorganic binder 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 matrix is suitable for serving as a corrosion barrier over an ultralong period of time.
  • the matrix is essentially free of pores, namely has a density which is preferably in the range of> 99% of the
  • the waste products can basically have any conceivable shape.
  • the waste products are preferably cylindrical. This is particularly true when the container has the preferred shape of a hexagonal prism.
  • the containers preferably have one
  • Wrench size from 400 to 600 mm and a preferred height of 800 to 1200 mm.
  • 210 waste compartments in the form of rods can be arranged in a trigonate 8-row design.
  • a part of it (5-10%) can be covered with absorber rods.
  • absorber material B 4 C can be used as absorber material B 4 C.
  • the graphite powder is preferably used with a particle diameter of ⁇ 30 ⁇ .
  • 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 by subsequent crushing and sieving a granulate with a grain size of less than 3.14 mm and greater than 0.31 mm is made.
  • a handle-resistant basic body with recesses for receiving metal-coated waste such as waste-containing composite-pressed rods or columns, is first pre-pressed.
  • 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 center impact.
  • a shaping rod part with a larger diameter which is placed on a thinner support rod.
  • Matrizenober the required filling space arises.
  • a pre-dosed granule portion is poured gleichmäOig, first precompressed 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 for the pre-pressed base body to be free of density over the entire length
  • both production steps, granule production and pre-pressing of the main 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.
  • 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 waste package according to the invention is based, for example, 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.
  • 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 compaction processes include, in addition to extrusion and the
  • the invention also relates to a waste compartment comprising a mixture of at least one waste product with glass in a metal shell.
  • this waste compartment has the properties of the waste compartments described above as part of the package.
  • Also according to the invention is the use of a container described above for storing radioactive waste.
  • the container is a prism made 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 pure natural graphite with a
  • 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 mold bars were removed from the top and the support bars pulled down.
  • 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.
  • fuel rod dummies (dummy fuel rods) were first pushed into tubular metal casings of copper at a gap width of about 1 mm. After sealing the tubes, they were processed by extrusion at 1000 ° C to composite-pressed, gap-free bars. Subsequently, the rods were formed into spiral bodies and, analogously to the production of the base bodies, embedded in layers into the graphite-glass granules. The final pressing of the waste packages is described in Example 1.

Landscapes

  • 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)

Abstract

L'invention concerne un colis servant au stockage de déchets radioactifs et approprié à un stockage final sûr et de très longue durée, ledit colis comprenant une matrice en graphite résistante à l'humidité et inoxydable et des déchets enveloppés de métal et noyés dans la matrice. L'invention concerne également un procédé de fabrication de tels colis.
EP11711513.9A 2010-03-25 2011-03-24 Procede pour la production des emballages pour le stockage des dechets Not-in-force EP2550664B1 (fr)

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 (fr) 2010-03-25 2011-03-24 Colis pour le stockage de déchets

Publications (2)

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

Family

ID=44279809

Family Applications (1)

Application Number Title Priority Date Filing Date
EP11711513.9A Not-in-force EP2550664B1 (fr) 2010-03-25 2011-03-24 Procede pour la production des emballages pour le stockage des dechets

Country Status (12)

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

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 (fr) 2021-09-13 2023-03-15 Behzad Sahabi Procédé de revêtement et dispositif de formation d'une couche barrière destinée à l'augmentation de l'imperméabilité et de la résistance à la corrosion, revêtement et emballage destinés à l'enrobage et au scellage des corps radioactifs pour le stockage définitif, ainsi que procédé de fabrication de l'emballage

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DE2551349C2 (de) * 1975-11-15 1985-08-08 Deutsche Gesellschaft für Wiederaufarbeitung von Kernbrennstoffen mbH, 3000 Hannover Verfahren zur Herstellung von Körpern mit hochradioaktive Abfallstoffe und/oder Aktinide enthaltendem Glasgranulat
DE2741661C2 (de) * 1977-09-16 1986-12-11 Gesellschaft für Strahlen- und Umweltforschung mbH, 8000 München Verfahren zur Umkleidung von Abfallfässern mit einer auslaugsicheren, geschlossenen Hülle
DE3103557A1 (de) * 1981-02-03 1982-12-09 Deutsche Gesellschaft für Wiederaufarbeitung von Kernbrennstoffen mbH, 3000 Hannover "transport- und lagerbehaelter fuer radioaktive abfaelle"
DE3144754A1 (de) * 1981-11-11 1983-05-19 Kernforschungszentrum Karlsruhe Gmbh, 7500 Karlsruhe Formkoerper zur einbindung radioaktiver abfaelle und verfahren zu seiner herstellung
DE3144755C2 (de) * 1981-11-11 1984-06-28 Nukem Gmbh, 6450 Hanau Formkörper zur Einbindung von abgebrannten Kernbrennstoffstäben und Verfahren zu seiner Herstellung
AT375207B (de) * 1982-03-02 1984-07-10 Solomon Paul Dipl Ing Herstellung von schutzueberzuegen auf radioaktiven abfaellen der kernenergie
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KR101173414B1 (ko) * 2008-11-10 2012-08-13 에이엘디 배큐움 테크놀로지스 게엠베하 방사성 폐기물의 최종 저장에 적합한 그라파이트 및 무기 결합제로 구성된 매트릭스 물질, 이를 제조하는 방법, 이를 처리하는 방법 및 이의 용도
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Also Published As

Publication number Publication date
CN102906822A (zh) 2013-01-30
EA023726B1 (ru) 2016-07-29
EA201201328A1 (ru) 2013-03-29
WO2011117354A1 (fr) 2011-09-29
UA105288C2 (ru) 2014-04-25
EP2550664B1 (fr) 2013-12-25
DE102010003289A1 (de) 2011-09-29
JP2013524165A (ja) 2013-06-17
KR101450016B1 (ko) 2014-10-15
JP5313412B2 (ja) 2013-10-09
CA2794405A1 (fr) 2011-09-29
CA2794405C (fr) 2014-02-04
DE102010003289B4 (de) 2017-08-24
KR20120125670A (ko) 2012-11-16
ES2454565T3 (es) 2014-04-10
US20130012374A1 (en) 2013-01-10
BR112012024304A2 (pt) 2019-09-24

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