EP0296855A2 - Lagermethode für radioaktives Abfallmaterial - Google Patents

Lagermethode für radioaktives Abfallmaterial Download PDF

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Publication number
EP0296855A2
EP0296855A2 EP88305733A EP88305733A EP0296855A2 EP 0296855 A2 EP0296855 A2 EP 0296855A2 EP 88305733 A EP88305733 A EP 88305733A EP 88305733 A EP88305733 A EP 88305733A EP 0296855 A2 EP0296855 A2 EP 0296855A2
Authority
EP
European Patent Office
Prior art keywords
vessel
inner vessel
radioactive waste
waste material
storing radioactive
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.)
Withdrawn
Application number
EP88305733A
Other languages
English (en)
French (fr)
Other versions
EP0296855A3 (de
Inventor
Eric John Ramm
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.)
Australian Nuclear Science and Technology Organization
Original Assignee
Australian Nuclear Science and Technology Organization
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
Priority claimed from US07/065,803 external-priority patent/US4834917A/en
Application filed by Australian Nuclear Science and Technology Organization filed Critical Australian Nuclear Science and Technology Organization
Publication of EP0296855A2 publication Critical patent/EP0296855A2/de
Publication of EP0296855A3 publication Critical patent/EP0296855A3/de
Withdrawn legal-status Critical Current

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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
    • G21F9/28—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

Definitions

  • the present invention relates to an encapsulation method suitable for safe storage of radioactive waste such as high level waste products, spent nuclear fuel rods, spent fuel and generally any radioactive product which is usually in a solid form.
  • the method is particularly directed to providing a containment structure which is readily susceptible to waste retrieval whereby the radioactive waste material can be retrieved for reprocessing at a later point in time.
  • One prior proposal is for immobilising the waste by mixing a calcine of the waste with synthetic rock precursor elements and subjecting the mixture to very high temperatures and pressures for extending periods of time to form a synthethic rock.
  • Methods for achieving this include hot isostatic pressing (for example as disclosed in U.S. patents 4,172,807 (Larker), 4,409,029 (Larker and Tegman) 4,642,204 (Burstrom and Tegman) and uniaxial pressing including hot upward uniaxial pressing using bellows-like containers (see U.S. patent 4,645,624 issued to Australian Atomic Energy Commission and The Australian National University).
  • a method of encapsulation of radioactive waste products which not only is directed to providing safe long term storage and containment, but also is specifically adapted to permit retrieval of the waste products at a much later date when reprocessing may be required.
  • Many high level types of radioactive waste contain very valuable components and after a period of many years storage, during which decay of certain components takes place, it may be desired to retrieve the material and reprocess.
  • a novel method for achieving such a containment is provided by a method which uses a substantially non-deformable inner vessel for containing the radioactive waste material securely during the method and during storage, the inner vessel being placed within a deformable outer vessel and a protective metal sheath (highly resistant to corrosion) being formed between the inner and outer vessels by placing in this zone metal material which has a substantially lower melting point than the inner vessel and the outer vessel and which is capable of forming a dense matrix; the method further comprises closing the outer vessel and subjecting the structure to sufficiently elevated temperature and pressure for sufficient time to compress the outer container and the metal material to form a dense sheath, whereby at any subsequent time the outer container may be opened and subjected to a heating process to remove the metal material, thereby releasing the inner vessel for removal of its contents.
  • the outer vessel has a cylindrical outer wall or a bellows like outer wall.
  • a non-deformable inner vessel retains safely radioactive waste and a suitable dense metal sheath is formed around the inner vessel at relatively low temperatures and pressures and, most importantly, the melting point of the material forming the sheath is substantially lower than the melting point of the inner vessel or the outer vessel so that the sheath can be removed in a suitable furnace thereby permitting retrieval of the inner vessel and the waste for reprocessing.
  • Figure 1 shows a cylindrical metal vessel 60 having domed ends with an aperture 61 at the top end for receiving high level radioactive waste in the form of calcine 63 and an annular collar 62 around the upper end of the vessel to permit it to be lifted and moved.
  • the vessel 60 is of a metal which is highly resistant to corrosion, substantially non-deformable in the process and retains high strength at temperatures in the process.
  • a suitable metal would be Inconel 601.
  • FIGs 3 and 4 show an alternative embodiment in which a large aperture 66 is provided at the top of the vessel whereby a bundle of spent nuclear fuel rods 67 can be inserted within the vessel.
  • the vessel is closed in a similar manner by a top cap 68, evacuated and sealed.
  • the inner vessel 60 is located within a cylindrical outer vessel 70 having a bellows-like side wall 71 and planar end walls 72 and 73.
  • copper powder 74 is used for forming the protective sheath since it is highly corrosive resistant, will form a dense matrix, is economic and has a suitably low melting point.
  • a perforated cylinder 75 of the same material namely copper is disposed in the central lower region of the bellows container 71 and supports the inner vessel 60.
  • a perforated annular disk 76 also of copper is provided in the upper region for centralising the inner vessel 60.
  • Figure 5 shows the assembly after the copper powder 74 has been poured into the space between the vessels, vibration assisting the establishment of a good packing density.
  • the top end wall 73 is welded into position and gases within the bellows container 71 evacuated through evacuation tube 77, which is then welded to seal the structure.
  • Hot isostatic pressing is conducted in this example, typical conditions being 800°C, 20 MPa and a time of about 1 hour.
  • the resultant end structure is generally as shown in Figure 6, the bellows container 71 being axially compressed but not disorted or substantially deformed in the radial direction.
  • a dense copper sheath 78 is formed between the vessels and provides a massive barrier for safe containment of the radioactive waste.
  • the copper sheath is highly corrosion resistant and can also conduct away heat generated during radioactive decay of the material in the inner vessel 60.
  • the outer bellows container 71 is formed of a metal having a good strength at high temperatures, a convenient metal being Inconel 601. However, safe containment of the radioactive material does not depend on the bellows container 71 as the copper sheath 78 is the essential safety element, even though normally the bellows container 71 will provide a reliable and complete containment structure.
  • Figure 7 illustrates the method of recovering the high level waste for reprocessing.
  • the base 72 of the bellows container 71 is removed and the assembly supported in an induction furnace having coils 80 and a suscepter sleeve 81.
  • the copper matrix 78 is melted and flows into a receiving crucible located below the furnace thereby releasing the inner vessel 60 for processing.
  • Providing the copper is not contaminated it may be re-used.
  • Figure 8 illustrates the inner vessel of Figure 1 having three annular strengthening collars 82.

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)
  • Gasification And Melting Of Waste (AREA)
EP88305733A 1987-06-23 1988-06-23 Lagermethode für radioaktives Abfallmaterial Withdrawn EP0296855A3 (de)

Applications Claiming Priority (2)

Application Number Priority Date Filing Date Title
US65803 1987-06-23
US07/065,803 US4834917A (en) 1986-06-25 1987-06-23 Encapsulation of waste materials

Publications (2)

Publication Number Publication Date
EP0296855A2 true EP0296855A2 (de) 1988-12-28
EP0296855A3 EP0296855A3 (de) 1989-12-06

Family

ID=22065212

Family Applications (1)

Application Number Title Priority Date Filing Date
EP88305733A Withdrawn EP0296855A3 (de) 1987-06-23 1988-06-23 Lagermethode für radioaktives Abfallmaterial

Country Status (1)

Country Link
EP (1) EP0296855A3 (de)

Cited By (3)

* Cited by examiner, † Cited by third party
Publication number Priority date Publication date Assignee Title
JPH0742483B2 (ja) * 1988-09-27 1995-05-10 オーストラリアン ニュークリア サイエンス アンド テクノロジー オーガニセイション 粒状物材料の高温圧縮
CN107464597A (zh) * 2017-08-30 2017-12-12 中广核研究院有限公司 强放射性工业钴源防泄漏封装结构及封装工艺
KR102004182B1 (ko) * 2018-10-31 2019-07-26 한국원자력환경공단 다중 방벽을 이용한 고준위 방사성 폐기물의 처분 용기 및 이를 이용한 방벽 시스템

Citations (3)

* Cited by examiner, † Cited by third party
Publication number Priority date Publication date Assignee Title
FR2375695A1 (fr) * 1976-12-21 1978-07-21 Asea Ab Procede pour le traitement de dechets radioactifs
US4588088A (en) * 1983-01-10 1986-05-13 Allen Arthur A Container assembly for storing toxic material
DE3731848A1 (de) * 1986-09-30 1988-04-14 Au Nuclear Scienc Tech Heights Verfahren zur einkapselung von abfallstoffen

Patent Citations (3)

* Cited by examiner, † Cited by third party
Publication number Priority date Publication date Assignee Title
FR2375695A1 (fr) * 1976-12-21 1978-07-21 Asea Ab Procede pour le traitement de dechets radioactifs
US4588088A (en) * 1983-01-10 1986-05-13 Allen Arthur A Container assembly for storing toxic material
DE3731848A1 (de) * 1986-09-30 1988-04-14 Au Nuclear Scienc Tech Heights Verfahren zur einkapselung von abfallstoffen

Cited By (5)

* Cited by examiner, † Cited by third party
Publication number Priority date Publication date Assignee Title
JPH0742483B2 (ja) * 1988-09-27 1995-05-10 オーストラリアン ニュークリア サイエンス アンド テクノロジー オーガニセイション 粒状物材料の高温圧縮
CN107464597A (zh) * 2017-08-30 2017-12-12 中广核研究院有限公司 强放射性工业钴源防泄漏封装结构及封装工艺
KR102004182B1 (ko) * 2018-10-31 2019-07-26 한국원자력환경공단 다중 방벽을 이용한 고준위 방사성 폐기물의 처분 용기 및 이를 이용한 방벽 시스템
WO2020091208A1 (ko) * 2018-10-31 2020-05-07 한국원자력환경공단 다중 방벽을 이용한 고준위 방사성 폐기물의 처분 용기 및 이를 이용한 방벽 시스템
US11309099B2 (en) 2018-10-31 2022-04-19 Korea Radioactive Waste Agency Disposal container for high-level radioactive waste using multiple barriers and barrier system using thereof

Also Published As

Publication number Publication date
EP0296855A3 (de) 1989-12-06

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