EP1103983A1 - Méthode pour le transport, l'empilement et le stockage des matières radioactives; conteneur blindé pour les matières radioactives et son procédé de fabrication - Google Patents

Méthode pour le transport, l'empilement et le stockage des matières radioactives; conteneur blindé pour les matières radioactives et son procédé de fabrication Download PDF

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Publication number
EP1103983A1
EP1103983A1 EP99830739A EP99830739A EP1103983A1 EP 1103983 A1 EP1103983 A1 EP 1103983A1 EP 99830739 A EP99830739 A EP 99830739A EP 99830739 A EP99830739 A EP 99830739A EP 1103983 A1 EP1103983 A1 EP 1103983A1
Authority
EP
European Patent Office
Prior art keywords
shell
jacket
lead
radioactive material
shielding
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
EP99830739A
Other languages
German (de)
English (en)
Other versions
EP1103983B1 (fr
Inventor
Bruno Pietrini
Fabio Pietrini
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.)
Sider Piombino Srl
Original Assignee
Sider Piombino Srl
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 Sider Piombino Srl filed Critical Sider Piombino Srl
Priority to EP99830739A priority Critical patent/EP1103983B1/fr
Priority to DE69917284T priority patent/DE69917284D1/de
Priority to AT99830739T priority patent/ATE266893T1/de
Publication of EP1103983A1 publication Critical patent/EP1103983A1/fr
Application granted granted Critical
Publication of EP1103983B1 publication Critical patent/EP1103983B1/fr
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
    • 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 the disposal of radioactive waste and more precisely it relates to a method for transporting, stacking and storing radioactive material.
  • the invention relates to a shielding shell that carries out this method.
  • the invention relates also to a process for the production of this shell.
  • One of the methods presently used is that of embedding the waste in a concrete matrix which, once solidified, forms a block.
  • the block in turn is put into a shielding shell of plain concrete, preferably baritic plain concrete .
  • the concrete matrix has the function of neutralising the waste and preventing it from the diffusion both volatile or in solution.
  • the shell has the object of creating an appropriate shielding barrier with respect to the gamma ray emitted by the radioactive waste, thus shielding both the operators and the environment.
  • the inert matrix and the waste are mixed directly in a metal container that is already located in the shell, equipped with a system of disposable blades that remain embedded in the block and are disposed of along with it.
  • the shell sealed with a lid made of the same material, is then carried with the block in it contained and disposed of, in appropriate areas.
  • the shell made of plain baritic concrete even if it has high shielding capacity with respect to other types of shielding means, has the following drawback:
  • the present invention one of whose characteristics is to provide a method for transporting, stacking and storing inertised radioactive material, wherein the inertised radioactive material is put into a shielding shell comprising a lead jacket of predetermined thickness.
  • the lead jacket has high shielding capacity and, in case of collision after fall of the shell, it is deformed plastically without break and substantially without varying its thickness, whereby both the isotropy and the shielding efficiency are assured.
  • a shell for shielding and containing inertised radioactive material has the characteristic of having walls comprising at least a lead shield of predetermined thickness.
  • the shell Opposite to the bottom plates the shell has a ring that connects the outer and inner cylindrical walls and that has holes for fastening a lid.
  • the outer bottom plate is connected to a cylindrical enlargement having function of frame base, the cylindrical enlargement having an inlet hole for casting from the outside molten lead in the interspace.
  • the inertised radioactive material comprises a concrete matrix solidified in an implemented container, having mixing blades rotatable with respect to a top plate.
  • the diameter of the implemented container is slightly less than the diameter of the inner cylindrical wall of the shell.
  • the top plate has preferably a thickness substantially equal to said predetermined thickness.
  • a method for the production of a shell for shielding radioactive substances comprises the steps of:
  • the interspace is formed between two co-axial cylindrical walls closed by distanced bottom plates according to a predetermined thickness of the lead, the inlet hole being executed at the bottom, whereby the interspace is filled overturning the shell and filling it through the bottom.
  • bleed of air is carried out through holes made in the interspace at the bottom.
  • a method for transporting, stacking and storing radioactive material is carried out according to the invention by means of a metallic implemented container 10 put in a cylindrical shielding shell 20.
  • the implemented container 10 comprises a containing wall 11 closed by a lid 12 having openings 13 for the introduction of a concrete mixture in which radioactive waste is embedded.
  • blades 14 are provided integral to a shaft 15 pivotally connected to lid 12 and are operated from the outside by means of a mechanical interface 16. The rotation of blades 14 allows a solidification of the concrete matrix this and the radioactive substances are uniformly dispersed in it.
  • container 10 is the system most frequently used for making inert radio waste, other known methods can be used to cast a block 17 of cylindrical shape suitable for being put into shell 20.
  • the latter comprises a jacket 21 in which lead 22 and/or a lead alloy is contained suitable for being cast.
  • jacket 21 is formed by an outer cylindrical wall 23 closed by an outer bottom plate 24 and by an inner cylindrical wall 25 closed by an inner bottom plate 26.
  • Spacers 27 and 28 are provided, for example distanced 120 degrees from one another, maintaining a substantially uniform thickness in lead 22.
  • a cylindrical enlargement 29 is welded having a central connection hole 30 between the outside and jacket 21.
  • small bleed holes 31 and 32 are provided respectively in bottom plate 24 and in cylindrical hollow enlargement 29.
  • Jacket 21 formed between the two inner cylindrical wall 25 and outer cylindrical wall 23 is closed at the top by a ring 33 having holes 34 for fastening screws not shown of a lid 35 for closing inner space 36, that is defined by inner cylindrical wall 25 and in which the block formed by implemented container 10 is housed.
  • Lid 35 has a flange 35a with holes 37 and notches 38 for fixing ring 33 by means of the screws.
  • Lid 35 can have also a lead plate for completing the shielding provided by the lead of shell 20.
  • lid 35 is made of steel and the shielding is completed by lid 12 of implemented container 10 shown also in figure 4.
  • shell 20 fell from a height H of 1.20 m, starting from a vertical axis position (A), a horizontal axis position (C) and an inclined axis position(B).
  • shell 20 and the implemented container 10 can be produced for example in carpentry working shops.
  • Shell 20, moreover, can be filled with lead along an appropriate plant described hereinafter.
  • the casting step of radioactive material into implemented container 10 and the introduction in shell 20 of the solidified blocks thus obtained is, instead, carried out directly from specialised operators for processing radioactive waste in the plants that have generated them, in order to avoid any pollution risk.
  • shell 20 is then overturned so that hole 30 is oriented towards the above. Then, molten lead 22a is cast through hole 30 in order to fill completely jacket 21.
  • the small holes 31 and 32 allow the bleed of air during the rise of the level 22b of the molten lead.
  • a cooling period is provided for lead 22 shrinkage, then the lead level is topped up to compensate .
  • carriage 40 is located in a region of inlet/outlet of empty/filled shells.
  • a carriage 40 with the empty shells runs on a track 41 for being put into a shell heating tunnel 42 up to a temperature close to that of molten lead .
  • shells 20 are carried under a lead sprue hole 43.
  • Lead has been molten in an oven 44 supplied with ingots 45 by means of a conveyor belt 46.
  • Sprue hole 43 carries out the filling step as shown in figure 6.
  • Shells 20, after a cooling period, are carried again by carriage 40 in turn under sprue hole 43 for topping up so that the room left by shrinkage of lead during the cooling step is filled.

Landscapes

  • Physics & Mathematics (AREA)
  • Engineering & Computer Science (AREA)
  • General Engineering & Computer Science (AREA)
  • High Energy & Nuclear Physics (AREA)
  • Processing Of Solid Wastes (AREA)
  • Packages (AREA)
EP99830739A 1999-11-29 1999-11-29 Méthode pour le transport, l'empilement et le stockage des matières radioactives; conteneur blindé pour les matières radioactives et son procédé de fabrication Expired - Lifetime EP1103983B1 (fr)

Priority Applications (3)

Application Number Priority Date Filing Date Title
EP99830739A EP1103983B1 (fr) 1999-11-29 1999-11-29 Méthode pour le transport, l'empilement et le stockage des matières radioactives; conteneur blindé pour les matières radioactives et son procédé de fabrication
DE69917284T DE69917284D1 (de) 1999-11-29 1999-11-29 Verfahren zum Transportieren, Stapeln und Lagern von radioaktiven Materialien, Abschirmbehälter für radioaktive Materialien und Behälterherstellungsverfahren
AT99830739T ATE266893T1 (de) 1999-11-29 1999-11-29 Verfahren zum transportieren, stapeln und lagern von radioaktiven materialien, abschirmbehälter für radioaktive materialien und behälterherstellungsverfahren

Applications Claiming Priority (1)

Application Number Priority Date Filing Date Title
EP99830739A EP1103983B1 (fr) 1999-11-29 1999-11-29 Méthode pour le transport, l'empilement et le stockage des matières radioactives; conteneur blindé pour les matières radioactives et son procédé de fabrication

Publications (2)

Publication Number Publication Date
EP1103983A1 true EP1103983A1 (fr) 2001-05-30
EP1103983B1 EP1103983B1 (fr) 2004-05-12

Family

ID=8243689

Family Applications (1)

Application Number Title Priority Date Filing Date
EP99830739A Expired - Lifetime EP1103983B1 (fr) 1999-11-29 1999-11-29 Méthode pour le transport, l'empilement et le stockage des matières radioactives; conteneur blindé pour les matières radioactives et son procédé de fabrication

Country Status (3)

Country Link
EP (1) EP1103983B1 (fr)
AT (1) ATE266893T1 (fr)
DE (1) DE69917284D1 (fr)

Cited By (2)

* Cited by examiner, † Cited by third party
Publication number Priority date Publication date Assignee Title
CN111524629A (zh) * 2019-02-03 2020-08-11 西安大医集团股份有限公司 一种屏蔽装置
CN119287302A (zh) * 2024-10-10 2025-01-10 湖北东特特种装备有限公司 一种压力容器全自动搪铅装置与工艺

Citations (4)

* Cited by examiner, † Cited by third party
Publication number Priority date Publication date Assignee Title
LU40315A1 (fr) * 1960-07-06 1961-08-26
FR1393704A (fr) * 1963-04-03 1965-03-26 Nat Lead Co Récipient pour éléments de combustible
FR1515024A (fr) * 1966-10-11 1968-03-01 Commissariat Energie Atomique Château de transport de produits radioactifs
FR2074726A7 (en) * 1970-01-22 1971-10-08 Robatel Slpi Composite packaging material esp - for radio chemicals

Patent Citations (4)

* Cited by examiner, † Cited by third party
Publication number Priority date Publication date Assignee Title
LU40315A1 (fr) * 1960-07-06 1961-08-26
FR1393704A (fr) * 1963-04-03 1965-03-26 Nat Lead Co Récipient pour éléments de combustible
FR1515024A (fr) * 1966-10-11 1968-03-01 Commissariat Energie Atomique Château de transport de produits radioactifs
FR2074726A7 (en) * 1970-01-22 1971-10-08 Robatel Slpi Composite packaging material esp - for radio chemicals

Non-Patent Citations (1)

* Cited by examiner, † Cited by third party
Title
J. KERJEAN ET AL./ P. BLUM ET AL.: "II. Les emballages pour le transport des matières radioactives", ENERGIE NUCLÉAIRE, vol. 9, no. 4, June 1967 (1967-06-01) - July 1967 (1967-07-01), pages 232 - 240, XP002138704 *

Cited By (3)

* Cited by examiner, † Cited by third party
Publication number Priority date Publication date Assignee Title
CN111524629A (zh) * 2019-02-03 2020-08-11 西安大医集团股份有限公司 一种屏蔽装置
CN119287302A (zh) * 2024-10-10 2025-01-10 湖北东特特种装备有限公司 一种压力容器全自动搪铅装置与工艺
CN119287302B (zh) * 2024-10-10 2025-05-06 湖北东特特种装备有限公司 一种压力容器全自动搪铅装置与工艺

Also Published As

Publication number Publication date
EP1103983B1 (fr) 2004-05-12
DE69917284D1 (de) 2004-06-17
ATE266893T1 (de) 2004-05-15

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