EP0843318A1 - Rillenanordnung zur Aussenkühlung von Behältern für radioaktive Stoffe - Google Patents

Rillenanordnung zur Aussenkühlung von Behältern für radioaktive Stoffe Download PDF

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Publication number
EP0843318A1
EP0843318A1 EP97420215A EP97420215A EP0843318A1 EP 0843318 A1 EP0843318 A1 EP 0843318A1 EP 97420215 A EP97420215 A EP 97420215A EP 97420215 A EP97420215 A EP 97420215A EP 0843318 A1 EP0843318 A1 EP 0843318A1
Authority
EP
European Patent Office
Prior art keywords
grooves
wall
container
steel
radioactive material
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Withdrawn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
EP97420215A
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English (en)
French (fr)
Inventor
Bernard Kirchner
Pierre Malesys
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.)
Societe pour les Transports de lIndustrie Nucleaire Transnucleaire SA
Original Assignee
Societe pour les Transports de lIndustrie Nucleaire Transnucleaire SA
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 Societe pour les Transports de lIndustrie Nucleaire Transnucleaire SA filed Critical Societe pour les Transports de lIndustrie Nucleaire Transnucleaire SA
Publication of EP0843318A1 publication Critical patent/EP0843318A1/de
Withdrawn legal-status Critical Current

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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
    • G21F5/00Transportable or portable shielded containers
    • G21F5/06Details of, or accessories to, the containers
    • G21F5/10Heat-removal systems, e.g. using circulating fluid or cooling fins

Definitions

  • the invention relates to a device for cooling the external surface of containers for transport or storage of radioactive materials, in particular fuel assemblies irradiated nuclear power, said cooling consisting in dissipating the thermal power generated by said radioactive materials packaged by convection in ambient air.
  • Radioactive materials especially. irradiated nuclear fuel assemblies, are usually transported and / or stored in containers (also called packaging) watertight cylindrical shape with very thick walls (several tens of cm), mainly base of cast iron or forged or cast steel, which provide holding functions mechanical (resistance to impact or severe falls), radiological protection, and transfer from the inside to the outside.
  • the walls can also be composite and include additional elements allowing improve container performance: for example resin, lead to improve the radiological protection, copper to improve heat transfer, etc.
  • Packaged radioactive material giving off heat, dissipating power temperature in the ambient air must be such that the components of the container and its contents are not brought in any place to temperatures prejudicial to their maintenance in an adequate state.
  • the main parameter on which we can play to dissipate the required thermal power is the surface area of the exposed container convection of ambient air.
  • the fins are spaced 5 to 10 cm apart and have a height, perpendicular to the outer surface, about 10 cm or more.
  • fins increases the overall size of the packaging and constitutes a serious handicap when there are severe constraints relating to the space or surface available where the packaging must be stored, handled or transported.
  • the presence of fins on the one hand can constitute contamination traps difficult to clean, in particular when the fins are fixed against the outer surface of the packaging, on the other hand can constitute a significant mass of material that 'It is not possible to take into account to carry out the radioactive shielding calculations because of the gamma radiation leaks which can occur between two consecutive fins if they are too far apart from each other.
  • the plaintiff has therefore sought how to increase the exchange surface by limiting increasing the size and ensuring that all of the material used is taken into account for the shielding.
  • the invention is a device for the external cooling of containers for the packaging of radioactive materials having an outer metal wall, characterized in that it has grooves made in the outer face of said wall.
  • the walls can be more or less thick (from a few cm to a few tens of cm thick) homogeneous or composite metals and generally based on steel or cast iron, but also aluminum, copper or their alloys.
  • the grooves are made directly in the outer face of the metal wall thick, or when the thick wall is covered with a neutron shield (for example at hydrogenated resin base), which in turn is covered with a metallic shell more thin (for example in sheet steel 10 to 30 mm thick), said grooves are practiced in the outer face of said envelope, the thermal continuity between the thick wall and the envelope then being usually produced using metal parts serving as thermal conductors and passing through the neutron shield.
  • a neutron shield for example at hydrogenated resin base
  • a metallic shell more thin for example in sheet steel 10 to 30 mm thick
  • the splines constituting the device according to the invention can be practiced there according to generating the cylindrical surface, so in a plane parallel to the axis of the cylinder, or according to the perimeter (or circumference) of said cross section, therefore in a plane perpendicular to the axis of the cylinder.
  • the splines can also be helical, rotating around the container in one direction, or the other, or both.
  • the spline device according to the invention therefore has very great flexibility since it can be adapted to the type of container used and to the manner of using it.
  • a container for storage will be used vertically and will have splines according to generators; on the other hand a container for transport will be used especially in horizontal position and will have a system of circumferential grooves, or a system of helical grooves wound in one direction or the other, or in both, which cannot be obtained with a conventional fin cooling system.
  • the splines can be engraved by machining (turning, milling %) or obtained directly by molding, extrusion or any other process.
  • the grooves are regularly spaced.
  • Their cross section (recessed in the wall metallic) is advantageously polygonal, preferably square or rectangular, to obtain better surface growth, but may have other profiles, for example circular etc ... They are separated from each other by a portion of the outer surface of the wall in relief in relation to the hollow grooves.
  • Figure 1 illustrates a composite wall of a straight section cylindrical container circular where the grooves according to the invention were made according to generators (parallel to the cylinder axis).
  • grooves (7) were made open and in contact with ambient air, rectangular section (in this case), of width (8), of depth (10) and whose re-entrant angles (9) are rounded.
  • the width (8) of the grooves is less than 30 mm and their depth (10) to 15 mm; under these conditions it is easy to obtain that no variation significant dose rate resulting from the presence of splines is not measurable as well on the surface of the container only 1 m or 2 m from its surface (as required by the regulations applicable): thus all the material of the wall or of the external envelope, after shaping of the splines, can actually be taken into account in the shielding calculations.
  • the grooves have sufficient efficiency for cooling by ambient air, it is advantageous that their width and depth are greater than 1 mm and preferably between 5 and 10 mm, so that air can circulate efficiently in said grooves.
  • the pitch of the grooves (that is to say the distance each of which should be moved to coincide with the next) must be determined in relation to their width and their depth according to the increase in surface area that the we want to get.
  • the pitch is between 1 and 50 mm, preferably between 10 mm and 20 mm.
  • the pitch must be greater than the width of the grooves.
  • longitudinal grooves with a rectangular cross section 10 mm wide, depth 5 mm in steps of 20 mm allow a 50% increase in the external surface of the container subjected to ambient air cooling, while the section grooves square right of the same width, 10 mm deep with 20 mm pitch allow an increase 100%.
  • a container with splines according to the invention will have the same weight and the same shielding performance than a container without a groove, while its cooling surface will be significantly increased and that its size (for example its diameter) will not be increased only a few mm.
  • a container having a smooth wall of the same thickness provided with fins 10 mm thick, 50 mm high, 100 mm pitch, providing a 100% increase in surface area, leading to an increase in overall diameter of 100 mm, the dose rate being determined by the zones between the fins; this means that the material of the fins cannot be taken into account in the shielding calculations and therefore constitutes a dead weight from this point of view.
  • the making of the grooves is much easier to make and less expensive, in particular by molding, extrusion or machining, because in this last case of their small dimensions and therefore the production of a quantity of chips scaled down. For the same reason decontamination is greatly facilitated, especially when the re-entrant angles of the grooves are rounded.
  • the invention can be used for any type of container intended for materials releasing a significant thermal power; it is particularly suitable for large containers dimensions, for example for transporting or storing a plurality of assemblies irradiated nuclear fuel, and in particular to containers with a wall of thick primary containment (20 to 50 cm) in steel or cast iron, possibly covered with a neutron shielding, generally made of hydrogenated resin, itself protected by an envelope steel which is generally several centimeters thick.

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  • Physics & Mathematics (AREA)
  • Engineering & Computer Science (AREA)
  • General Engineering & Computer Science (AREA)
  • High Energy & Nuclear Physics (AREA)
  • Packages (AREA)
  • Gasket Seals (AREA)
EP97420215A 1996-11-19 1997-11-18 Rillenanordnung zur Aussenkühlung von Behältern für radioaktive Stoffe Withdrawn EP0843318A1 (de)

Applications Claiming Priority (2)

Application Number Priority Date Filing Date Title
FR9614487 1996-11-19
FR9614487A FR2756090A1 (fr) 1996-11-19 1996-11-19 Dispositif a cannelures pour le refroidissement exterieur de conteneurs pour matieres radioactives

Publications (1)

Publication Number Publication Date
EP0843318A1 true EP0843318A1 (de) 1998-05-20

Family

ID=9498052

Family Applications (1)

Application Number Title Priority Date Filing Date
EP97420215A Withdrawn EP0843318A1 (de) 1996-11-19 1997-11-18 Rillenanordnung zur Aussenkühlung von Behältern für radioaktive Stoffe

Country Status (2)

Country Link
EP (1) EP0843318A1 (de)
FR (1) FR2756090A1 (de)

Cited By (2)

* Cited by examiner, † Cited by third party
Publication number Priority date Publication date Assignee Title
WO2004017331A1 (ja) * 2002-07-23 2004-02-26 Mitsubishi Heavy Industries, Ltd. キャスク及びキャスクの製造方法
FR2872956A1 (fr) * 2004-07-12 2006-01-13 Cogema Logistics Sa Dispositif externe d'evacuation de chaleur pour emballage destine au stockage et/ou au transport de matieres nucleaires

Citations (6)

* Cited by examiner, † Cited by third party
Publication number Priority date Publication date Assignee Title
DE1960536A1 (de) * 1969-12-03 1971-06-16 Kernforschungsanlage Juelich Heizbares Rohr oder aufheizbarer Stab zum konvektiven Waermetausch mit der Umgebung
BE875144A (nl) * 1979-03-28 1979-07-16 Belgonucleaire Nv Container voor het vervoer van warmte afgevende materialen
DE3206705A1 (de) * 1982-02-25 1983-09-01 Anton J. 7302 Ostfildern Vox Behaelter zum lagern und/oder transportieren von radioaktiven substanzen, insbesondere brennelemente
EP0301121A1 (de) * 1987-07-30 1989-02-01 Wieland-Werke Ag Rippenrohr
DD272981A3 (de) * 1987-07-08 1989-11-01 Germania Chemnitz Transportbehaelter fuer abgebrannte kernbrennstoffkassetten
JPH04204000A (ja) * 1990-11-29 1992-07-24 Kobe Steel Ltd 放射線遮蔽容器

Patent Citations (6)

* Cited by examiner, † Cited by third party
Publication number Priority date Publication date Assignee Title
DE1960536A1 (de) * 1969-12-03 1971-06-16 Kernforschungsanlage Juelich Heizbares Rohr oder aufheizbarer Stab zum konvektiven Waermetausch mit der Umgebung
BE875144A (nl) * 1979-03-28 1979-07-16 Belgonucleaire Nv Container voor het vervoer van warmte afgevende materialen
DE3206705A1 (de) * 1982-02-25 1983-09-01 Anton J. 7302 Ostfildern Vox Behaelter zum lagern und/oder transportieren von radioaktiven substanzen, insbesondere brennelemente
DD272981A3 (de) * 1987-07-08 1989-11-01 Germania Chemnitz Transportbehaelter fuer abgebrannte kernbrennstoffkassetten
EP0301121A1 (de) * 1987-07-30 1989-02-01 Wieland-Werke Ag Rippenrohr
JPH04204000A (ja) * 1990-11-29 1992-07-24 Kobe Steel Ltd 放射線遮蔽容器

Non-Patent Citations (1)

* Cited by examiner, † Cited by third party
Title
PATENT ABSTRACTS OF JAPAN vol. 016, no. 536 (P - 1449) 6 November 1992 (1992-11-06) *

Cited By (6)

* Cited by examiner, † Cited by third party
Publication number Priority date Publication date Assignee Title
WO2004017331A1 (ja) * 2002-07-23 2004-02-26 Mitsubishi Heavy Industries, Ltd. キャスク及びキャスクの製造方法
EP1524673A1 (de) * 2002-07-23 2005-04-20 Mitsubishi Heavy Industries, Ltd. Fass und verfahren zu seiner herstellung
EP1524673A4 (de) * 2002-07-23 2007-08-08 Mitsubishi Heavy Ind Ltd Fass und verfahren zu seiner herstellung
CN100337286C (zh) * 2002-07-23 2007-09-12 三菱重工业株式会社 屏蔽罐及屏蔽罐的制造方法
FR2872956A1 (fr) * 2004-07-12 2006-01-13 Cogema Logistics Sa Dispositif externe d'evacuation de chaleur pour emballage destine au stockage et/ou au transport de matieres nucleaires
WO2006016082A1 (fr) * 2004-07-12 2006-02-16 Tn International Dispositif externe d'evacuation de chaleur pour emballage destine au stockage et/ou au transport de matieres nucleaires

Also Published As

Publication number Publication date
FR2756090A1 (fr) 1998-05-22

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