EP0215552A2 - Warmverdichtung von Balgbehältern - Google Patents

Warmverdichtung von Balgbehältern Download PDF

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Publication number
EP0215552A2
EP0215552A2 EP86305337A EP86305337A EP0215552A2 EP 0215552 A2 EP0215552 A2 EP 0215552A2 EP 86305337 A EP86305337 A EP 86305337A EP 86305337 A EP86305337 A EP 86305337A EP 0215552 A2 EP0215552 A2 EP 0215552A2
Authority
EP
European Patent Office
Prior art keywords
canister
discharge duct
wall
metal
filter
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
EP86305337A
Other languages
English (en)
French (fr)
Other versions
EP0215552A3 (en
EP0215552B1 (de
Inventor
Eric John Ramm
Wilhelmus Joseph Bukyx
John Gemmell Padgett
Alfred Edward Ringwood
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 National University
Australian Nuclear Science and Technology Organization
Original Assignee
Australian Atomic Energy Commission
Australian National University
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
Application filed by Australian Atomic Energy Commission, Australian National University, Australian Nuclear Science and Technology Organization filed Critical Australian Atomic Energy Commission
Priority claimed from AU60187/86A external-priority patent/AU588612B2/en
Publication of EP0215552A2 publication Critical patent/EP0215552A2/de
Publication of EP0215552A3 publication Critical patent/EP0215552A3/en
Application granted granted Critical
Publication of EP0215552B1 publication Critical patent/EP0215552B1/de
Anticipated expiration legal-status Critical
Expired - Lifetime 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

Definitions

  • the present invention relates to removal of gases from a compressible, substantially closed container during hot uniaxial pressing and, in particular but not exclusively, is related to such a method for use in a process for immobilising high level radioactive nuclear waste material in a synthetic rock formed under heat and high pressure from an intimate mixture of such a waste material and synthetic rock-forming material.
  • These materials may be poured into a compressible, bellows-type canister which is closed and then subjected to hot uniaxial pressing such as described in our co-pending European Patent Application Nos. 81303221.6 and 83304974.5.
  • a known alternative to the present applicants' hot uniaxial pressing process is a hot isostatic processing in which the particulate waste material and synthetic rock forming material is placed in a metal container which needs to be evacuated and completely sealed. This metal container is then subjected to high temperatures with a very high surrounding gas pressure to cause compaction of the material within the canister as it forms a synthetic rock.
  • the canister is supported on all sides by the gas pressure and the very nature of the process is such that any gaseous material within the container must be retained therein.
  • the present invention concerns a development of the process of hot uniaxial pressing of the present applicants and in contrast to the hot isostatic pressing process proposes an arrangement whereby gases occuring within the container are removed in a controlled manner.
  • a method of forming synthetic rock incorporating radioactive waste wherein precursor materials for the synthetic rock mixed with radioactive waste are placed in a metal canister (1), the wall of which includes a bellows-like wall structure (3), the method comprising heating the canister (1) and its contents and maintaining a sufficiently elevated temperature during the application of axial pressure to the canister to cause the formation of synthetic rock and the discharge of gases, and characterised by using a canister including a discharge duct (8) connected to an exhaust gas processing system for discharging gases from within the canister (1).
  • the method preferably extends to connecting the discharge duct of the canister to an exhaust gas processing system whereby any necessary processing steps such as filtering of radioactive gasses can take place.
  • a metal canister for use in a hot pressing process for immobilising high level radioactive nuclear waste material
  • the canister (1) being adapted to be filled by a particulate material comprising radioactive waste and precursor materials for forming synthetic rock, the canister (1) being adapted to be closed after the particulate material has been poured into the canister (1), the canister (1) having a bellows-like wall (3) structure and characterised by the canister (1) having a gas discharge duct (8) adapted to be connected to a gas processing system when the canister, after being filled with particulate material, is subjected to high temperatures and/or axial compression.
  • the discharge duct is arranged to co-operate with a filter structure capable of retaining good gas permeability at high temperature, with the filter being arranged to prevent any solid material escaping from the canister during densification of material being compressed therein.
  • the filter structure advantageously comprises a cap-like structure having apertures therein and co-operating with a base end wall of the canister which has an aperture therein leading to the discharge duct, a cavity being defined between the aperture and the cap and incorporating a filter material whereby ingress of synthetic rock forming materials into the filter during compression of the canister is substantially avoided.
  • the discharge duct is preferably in the form of a bore extending through the base end wall of the canister and terminating in a pipe adapted to be connected to a gas processing system.
  • the discharge duct could be provided by a slot-like recess in the bottom of the base end wall of the canister, the duct in an operating position being closed by co-operation with an upper face of a pressure pad located on the hydraulic ram.
  • the canister optionally may include a cylindrical screen confining the particulate rock forming material and radioactive waste to a central zone of the canister and preventing the ingress of this material into the region of the convolutions of the bellows-like structure in the cylindrical side wall.
  • the zone between the exterior of the screen and the convoluted side wall could be left free of solid material or alternatively could receive granulated Zircaloy from spent nuclear fuel rods. In either case removal of gas from the region between the screen and the convoluted wall portion can be provided by apertures in the base end wall of the canister connecting to the discharge duct.
  • the discharge duct terminates in a pipe which communicates with a gas extraction manifold, for example by the aperture at the end of the pipe being disposed adjacent the opening to the manifold, a suction being maintained to cause reliable scavenging of all discharged gases.
  • this outlet pipe is an L-shaped pipe fitting having a horizontal limb rotatably mounted in sealing engagement in the base end wall of the canister and connected to the discharge duct; an arm of the L-shaped pipe fitting extending at right angles to this horizontal limb is adapted to be rotated from a upwardly directed transport position to a downwardly directed location by pivotal action whereby the open tip of the pipe is inserted through a slot in a side wall of an upwardly directed tube forming the manifold for the extraction system.
  • This tube is conveniently attached to the side of the pressure pad structure of the hydraulic ram.
  • Other configurations can be used.
  • a compressible, bellows-type metal canister 1 for use in a hot pressing process for immobilising high level radioactive nuclear waste material in the form of a synthetic rock.
  • the canister typically is generally as described in co-pending application no. 45384/80.
  • the canister includes a gas filter and discharge arrangement constituting one embodiment of the invention.
  • the canister 1 comprises a base wall 2 and a corrugated bellows-like side wall 3 of generally circular cross-section. Concentrically arranged within the corrugated side wall 3 is a cylindrical liner 4. In the centre of the base wall 2 is located a conically tapered aperture 5 provided with a filter plug shown diagrammatically at 6.
  • filter plug 6 which may be used in association with the central aperture 5 in the base wall 2 of the compressible canister 1.
  • the filter plug 6 in Figure 3A comprises an inverted castellated cap 9 with which is associated a filter mass 10 made of alumina or titania fibre.
  • This filter material is packed into the conically-tapered aperture 5 and into the gaps between the castellations of the cap 9.
  • the projecting lugs of the castellated cap 9 rest on the upper surface of the base wall 2 around the periphery of the conical-aperture 5 and thus compressive forces in the axial direction of the canister are absorbed and ingress of synthetic rock forming components into the filter structure are substantially avoided.
  • the filter plug 6 shown in Figure 3B differs from that of Figure 3A only in that it has a filter disc 10' made of Hastalloy in place of the mass of alumina or titania fibre.
  • the filter disc 10' is welded around its periphery as shown at 16 to the conical-aperture 5.
  • the outlet duct 8 is formed by the co-operation of a slot in the underside of the base wall 2, the duct being closed on its lower side by co-operation with the upper face of pressure pad 12 resting on a hydraulic ram.
  • the discharge of gases through the outlet duct 8 can be to a gas processing system of the type described below with reference to Figures 4A and 4B.
  • the gases will comprise the gas in the interstices of the particulate material in the canister and any volatile components produced from the particulate material during the heating stage.
  • the outlet pipe 8 (or outlet duct) is connected to an outlet tube 11.
  • the compressible canister 1 is shown in a free-standing position upon a lower pressure pad 12 of a hydraulic press associated with an induction furnace (not shown) in which the canister is to be heated to a high temperature and then compressed axially.
  • the outlet tube 11 is L-shaped and has its horizontal limb rotatably but sealingly mounted in a side of the base wall 2; the terminal limb in the illustrated loading position extends upwardly, with its open end free to the atmosphere.
  • the compressible bellows-type canister 1 is raised by the hydraulic ram to place the upper wall 17 of the canister against a fixed refractory abutment pad 13.
  • the canister is thus positioned so as to be heated in the induction furnace (not shown) which surrounds the canister.
  • the outlet tube 11 is rotated through 180° into a downwardly extending position, such that the terminal limb extends into a manifold arrangement 14 communicating with an exhaust tube 15. which is connected to a low pressure gas filtration system.
  • the manifold arrangement 14 and associated down pipe 15 are mounted on the lower pressure pad 12. so that they can move in unison with the exhaust tube 11 and canister 1 supported on that pad.
  • the high level radioactive nuclear waste incorporated into the synthetic rock materials includes elements volatile at the typical temperatures to which the material is heated (about 1150°C) it has been found that little, if any of these components are infact exhausted from the canister; it is thought these volatile components are absorbed into the synthetic rock materials.
  • the filter structure has a filter material for preventing the ejection of any particulate matter from the canister which might be entrained with the gases. Due to the gas collection system shown in Figures 4A and 4B the gaseous stream can be filtered and any radioactive components removed.
  • Figure 4A shows the loading postion.
  • the terminal limb 11 of the outlet duct is directed upwardly to prevent damage or catching on any objects.
  • the limb is rotated downwardly to engage in the slotted open end of manifold 14 which together with discharge pipe 15 are fixed to the side of the pressure pad 12.

Landscapes

  • Engineering & Computer Science (AREA)
  • Environmental & Geological Engineering (AREA)
  • Physics & Mathematics (AREA)
  • General Engineering & Computer Science (AREA)
  • High Energy & Nuclear Physics (AREA)
  • Filling Or Discharging Of Gas Storage Vessels (AREA)
EP19860305337 1985-07-16 1986-07-11 Warmverdichtung von Balgbehältern Expired - Lifetime EP0215552B1 (de)

Applications Claiming Priority (3)

Application Number Priority Date Filing Date Title
AU1498/85 1985-07-16
AUPH149885 1985-07-16
AU60187/86A AU588612B2 (en) 1985-07-16 1986-07-15 Hot pressing of bellows-like canisters

Publications (3)

Publication Number Publication Date
EP0215552A2 true EP0215552A2 (de) 1987-03-25
EP0215552A3 EP0215552A3 (en) 1989-08-30
EP0215552B1 EP0215552B1 (de) 1994-03-23

Family

ID=25632705

Family Applications (1)

Application Number Title Priority Date Filing Date
EP19860305337 Expired - Lifetime EP0215552B1 (de) 1985-07-16 1986-07-11 Warmverdichtung von Balgbehältern

Country Status (1)

Country Link
EP (1) EP0215552B1 (de)

Cited By (3)

* Cited by examiner, † Cited by third party
Publication number Priority date Publication date Assignee Title
DE3720731A1 (de) * 1986-06-25 1988-01-07 Atomic Energy Of Australia Einkapselung von abfallstoffen
EP0420719A3 (en) * 1989-09-28 1992-02-26 Kabushiki Kaisha Kobe Seiko Sho Also Known As Kobe Steel Method of evacuating radioactive waste treating container to vacuum
CN109690694A (zh) * 2016-07-08 2019-04-26 萨尔瓦托雷·莫里卡 主动加热炉隔离腔室

Family Cites Families (2)

* Cited by examiner, † Cited by third party
Publication number Priority date Publication date Assignee Title
US3160502A (en) * 1960-10-10 1964-12-08 American Beryllium Company Inc Method of making beryllium billets
SE442562B (sv) * 1983-01-26 1986-01-13 Asea Ab Sett att innesluta radioaktivt eller annat farligt avfall och en behallare for sadant avfall

Cited By (4)

* Cited by examiner, † Cited by third party
Publication number Priority date Publication date Assignee Title
DE3720731A1 (de) * 1986-06-25 1988-01-07 Atomic Energy Of Australia Einkapselung von abfallstoffen
EP0420719A3 (en) * 1989-09-28 1992-02-26 Kabushiki Kaisha Kobe Seiko Sho Also Known As Kobe Steel Method of evacuating radioactive waste treating container to vacuum
CN109690694A (zh) * 2016-07-08 2019-04-26 萨尔瓦托雷·莫里卡 主动加热炉隔离腔室
CN109690694B (zh) * 2016-07-08 2023-11-17 萨尔瓦托雷·莫里卡 主动加热炉隔离腔室

Also Published As

Publication number Publication date
EP0215552A3 (en) 1989-08-30
EP0215552B1 (de) 1994-03-23

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