EP0087350A1 - Neutron shielding device for radio-active material - Google Patents

Neutron shielding device for radio-active material Download PDF

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Publication number
EP0087350A1
EP0087350A1 EP83400285A EP83400285A EP0087350A1 EP 0087350 A1 EP0087350 A1 EP 0087350A1 EP 83400285 A EP83400285 A EP 83400285A EP 83400285 A EP83400285 A EP 83400285A EP 0087350 A1 EP0087350 A1 EP 0087350A1
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EP
European Patent Office
Prior art keywords
envelope
neutron
protection device
around
enclosure
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
EP83400285A
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German (de)
French (fr)
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EP0087350B1 (en
Inventor
Fernand Solignat
Gabriel Merle
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.)
Areva NP SAS
Original Assignee
Creusot Loire SA
Framatome SA
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Publication date
Application filed by Creusot Loire SA, Framatome SA filed Critical Creusot Loire SA
Priority to AT83400285T priority Critical patent/ATE19560T1/en
Publication of EP0087350A1 publication Critical patent/EP0087350A1/en
Application granted granted Critical
Publication of EP0087350B1 publication Critical patent/EP0087350B1/en
Expired legal-status Critical Current

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    • 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
    • G21F5/008—Containers for fuel elements

Definitions

  • the present invention relates to a neutron protection device for a radioactive product, such as a nuclear fuel, allowing good evacuation of the heat produced by this product.
  • the invention applies in particular to containers for radioactive products.
  • Radioactive products such as nuclear fuels
  • Such containers generally consist of a tight cylindrical envelope of great thickness.
  • Such an enclosure must be designed to mechanically resist accidental shocks, to constitute at the same time a protective screen against radioactive radiation, and finally to allow the evacuation of the heat produced by the radioactive material.
  • the envelope is generally not sufficient, and provision is often made to surround this envelope with a relatively thick layer made of a material absorbing the neutrons, such as a special resin.
  • the evacuation of the heat produced permanently by the radioactive material enclosed in the container there is generally provided a multitude of fins or plates distributed all around the cylindrical envelope and intended to evacuate in the ambient air calories by natural convection.
  • the material intended to absorb neutrons is generally a poor thermal conductor, and since it is generally interposed between the cylindrical envelope and the cooling fins, the evacuation of the heat is relatively poor.
  • the operation consisting in applying a large thickness of resin around the cylindrical envelope is an operation which is difficult to carry out, which can cause detachments due to shrinkage during its drying.
  • a container thus produced also has the serious drawback that the resin is exposed to accelerated aging as well as to accidental impacts which can cause cracks.
  • the present invention aims to overcome all these drawbacks.
  • the present invention therefore relates to a neutron protection device covering the external wall of an envelope of a receptacle enclosing a radioactive product, this device essentially comprising a neutron absorbing material disposed around the envelope of the receptacle.
  • this device further comprises a plurality of identical elements having the general shape of curved sheet metal strips, of constant profile over their entire length, these strips being regularly arranged all around the envelope and connected to it so as to provide closed cavities juxtaposed all around the envelope, the neutron absorbing material being introduced into said cavities thus formed.
  • each of these sheet metal strips extends parallel to its envelope, has an elongated rectangular shape and each has a folding at a certain angle along a line parallel to its lateral edges.
  • These bands are on the other hand arranged one beside the other around the cylindrical envelope, one lateral edge of each band being connected, over its entire length, to the cylindrical envelope, and the other lateral edge of each band. being connected, over its entire length, to the next strip.
  • FIG. 1 there is a cylindrical casing 1 of steel, very thick, and which defines an internal volume cylin drique 2 in which can be placed radioactive elements such as nuclear fuel elements.
  • the cylindrical envelope 1 is thick enough to prevent the propagation of most of the radioactive radiation as well as to mechanically resist any conceivable accidental shock.
  • On the external face 3 of this envelope are arranged a series of strips of welding by strip 5 regularly spaced and along generatrices of this cylindrical envelope 1. All around this cylindrical envelope, are then arranged elements 4, all identical, made from sheets of material which is a good thermal conductor, for example copper.
  • Each of these elements 4 consists of a rectangular strip, of length substantially equal to the length of the cylindrical envelope 1.
  • each metal strip 4 is welded in 15 along a corresponding strip welding seam 5; from this edge 6, the element 4 extends towards the outside in a first flat part 7 folded a first time, longitudinally, along a line 8, to be brought back in a circumferential plane, folded in the other direction along a second line 9 parallel to line 8, then folded along a third parallel line 10 in the same way as the first fold 8, so that the part 11 of the element is located circumferentially.
  • element 4 Due to the three parallel close folds 8, 9, 10, element 4 is given a general dihedral shape, the two sides of which are formed by parts 7 and 11, and, more precisely, in the zone common to parts 7 and 11, a groove 25 of small dimension is produced, also in the form of a dihedral.
  • the element 4 comprises, on the other hand, a lateral edge 12 welded to the next element 4, this edge 12 coming to fit in the groove 25 produced by means of reverse folding 9.
  • the dimension of this groove 25, in the radial direction is equal to the thickness of the part 11 of the element so that the external faces 13 of the peripheral parts 11 of the elements 4 are in the extension one of the 'other to constitute a perfect cylindrical wall, devoid of notches.
  • a weld 14 is then produced which connects the edge 12 of an element 4 with the next element 4, filling the remaining space of the groove 25, which thus constitutes a sealed external cylindrical wall.
  • the elements 4 are made from cut and folded sheets, but they can also be designed from forged, molded or machined materials.
  • the two welds 14 and 15 are easy to make because the access is not hampered by other elements 4. It can also be noted that, when one has welded at its two ends 6 and 12 an element 4, it constitutes a sealed space 16 delimited by the external wall 3 of the cylindrical envelope 1, by the internal faces of the parts 7 and 11 of an element 4, as well as by the external face of the part 7 of the 'element 4 above.
  • the tight spaces 16 can be filled, the access of one of the two ends of which is left free, with a neutron absorbing material, known per se.
  • a container as described above is particularly effective because, all around its cylindrical envelope 1, is arranged a neutron absorbing material which fills all the spaces 16 which are juxtaposed.
  • the neutron absorbing material therefore constitutes a practically continuous layer all around the cylindrical envelope 1, this layer is however interrupted by the metal parts 7 of the elements 4. For this reason, it is moreover recommended, as shown in FIG. 1, not to arrange these parts 7 exactly radially, but to incline them slightly by a certain angle oc relative to a radial direction 17.
  • a container in accordance with the present invention is also capable of efficiently dissipating the heat produced by the radioactive elements stored in the chamber 2.
  • the cylindrical envelope 1 is placed in communication with the external cylindrical wall formed by the parts 11 of the elements 4, using all the parts 7 of the elements 4. It can therefore be seen that the heat from the cylindrical envelope 1 can be easily transmitted to the parts 7 of the elements 4, then to the parts 11 of these elements 4 which are directly in contact with the ambient air. If, for example, the heat from the external wall formed by the parts 11 is removed by natural convection, it is possible to extract a high calorific power from the cylindrical envelope 1.
  • each element 11 a multitude of radial fins 18 welded to the elements 11. It is of course preferable to weld these fins 18 on the parts 11 before filling the cavities 16 with the neutron absorbing material.
  • the longitudinal cavities 16 filled with neutron absorbing material open out at the ends into annular cavities 19, 20 which are themselves filled with neutron absorbing material, annular sheets 21, 22 sealingly connecting the ends of the cylindrical wall 11 and the ends 23, 24 of the cylindrical envelope 1.
  • the neutron absorbing material is entirely enclosed in a sealed envelope, one can thus immerse in a swimming pool such a container avoiding any risk of water entering the neutron absorbing material.
  • this material resists aging much longer than if it were exposed to the open air.
  • the profiles 7 can also extend over the entire length of the container (as shown in Figure 3). In this case, the elements 21 and 22 do not exist, the ends 23, 24 of the envelope directly close off the ends of the cavities 16.
  • cooling fins 18 are also possible to design the cooling fins 18 as an integral part of the elements 4. To do this, it suffices to provide for each element 4 a radial extension towards the outside at the end 12 of these elements 4.

Abstract

1. Neutron-shielding device covering the outer wall of the enclosure of a receptacle containing a radioactive product, said device essentially comprising a neutro-absorbing substance arranged round the enclosure of the receptacle and a plurality of identical members (4) which have the general shape of a single strip of sheet metal extending with its largest dimension along the generatrices of the enclosure of the receptacle and whose cross-section has a curved outline continuing over its entire length, the said identical members being arranged uniformly all around and following radial directions relative to the axis of symmetry of the enclosure of the receptacle and having one of their edges, taken along the largest dimension of the sheet metal strips, connected directly to the enclosure, which device is characterized in that each member (4) is connected to the following member (4) and the members (4) are connected to the enclosure (1) so that they form, all around the enclosure (1), closed, adjoining cavities (16) in which three of the four walls which are parallel to the axis of the device consist of the two members (4) and in which the fourth consists of the enclosure (1), and the neutro-absorbing substance is enclosed in the said cavities (16) which are thus formed.

Description

La présente invention concerne un dispositif de protection neutronique pour un produit radio-actif, tel qu'un combustible nucléaire, permettant une bonne évacuation de la chaleur produite par ce produit. L'invention s'applique notamment aux conteneurs pour produits radio-actifs.The present invention relates to a neutron protection device for a radioactive product, such as a nuclear fuel, allowing good evacuation of the heat produced by this product. The invention applies in particular to containers for radioactive products.

Les produits fortement radio-actifs, tels que les combustibles nucléaires sont délicats à stocker ou à transporter parce qu'ils émettent des rayonnements dont il faut empêcher la propagation et parce qu'ils produisent en même temps une quantité de chaleur qu'il faut évacuer en permanence.Highly radioactive products, such as nuclear fuels, are difficult to store or transport because they emit radiation which must be prevented from spreading and because at the same time they produce a quantity of heat which must be removed. permanently.

De tels conteneurs sont généralement constitués d'une enveloppe cylindrique étanche de forte épaisseur. Une telle enceinte doit être étudiée pour résister mécaniquement à des chocs accidentels, pour constituer en même temps un écran de protection contre les rayonnements radio-actifs, et enfin pour permettre l'évacuation de la chaleur produite par la matière radio-active.Such containers generally consist of a tight cylindrical envelope of great thickness. Such an enclosure must be designed to mechanically resist accidental shocks, to constitute at the same time a protective screen against radioactive radiation, and finally to allow the evacuation of the heat produced by the radioactive material.

En ce qui concerne la protection contre les rayonnements radio-actifs, l'enveloppe ne suffit généralement pas, et il est souvent prévu d'entourer cette enveloppe d'une couche relativement épaisse constituée d'une matière absorbant les neutrons, telle qu'une résine spéciale.As regards protection against radioactive radiation, the envelope is generally not sufficient, and provision is often made to surround this envelope with a relatively thick layer made of a material absorbing the neutrons, such as a special resin.

En ce qui concerne l'évacuation de la chaleur produite en permanence par la matière radio-active enfermée dans le conteneur, il est prévu généralement une multitude d'ailettes ou de plaques réparties tout autour de l'enveloppe cylindrique et destinées à évacuer dans l'air ambiant les calories par convexion naturelle. Or comme la matière destinée à absorber les neutrons est généralement un mauvais conducteur thermique, et qu'elle se trouve en général interposée entre l'enveloppe cylindrique et les ailettes de refroidissement, l'évacuation de la chaleur se fait relativement mal.As regards the evacuation of the heat produced permanently by the radioactive material enclosed in the container, there is generally provided a multitude of fins or plates distributed all around the cylindrical envelope and intended to evacuate in the ambient air calories by natural convection. However, since the material intended to absorb neutrons is generally a poor thermal conductor, and since it is generally interposed between the cylindrical envelope and the cooling fins, the evacuation of the heat is relatively poor.

Par ailleurs, lorsque de tels conteneurs sont utilisés pour le transport de combustibles nucléaires, ces conteneurs peuvent être exposés à l'humidité ambiante ou aux intempéries. Dans ces conditions, la résine absorbant les neutrons qui entoure l'enveloppe cylindrique se trouve en contact avec l'humidité, et il a été fréquemment observé des infiltrations d'eau dans des fissures qui se forment dans la résine, lorsque celle-ci accuse un certain vieillissement. Un tel conteneur devient alors relativement dangereux parce que, même après un lavage et un séchage de sa face externe, l'eau qui s'est infiltrée dans la résine et qui est devenue radio-active resue pendant un temps assez long, présentant ainsi un danger de contamination.Furthermore, when such containers are used for the transport of nuclear fuels, these containers may be exposed to ambient humidity or to bad weather. Under these conditions, the neutron absorbing resin which surrounds the cylindrical envelope is in contact with moisture, and water has been frequently observed in cracks which form in the resin, when the latter shows some aging. Such a container then becomes relatively dangerous because, even after washing and drying its external face, the water which has infiltrated into the resin and which has become radioactive remains during a fairly long time, thus presenting a danger of contamination.

Par ailleurs, l'opération consistant à appliquer une forte épaisseur de résine autour de l'enveloppe cylindrique est une opération difficile à réaliser,pouvant entrainer des décollements à cause du retrait lors de son séchage. Un conteneur ainsi réalisé présente aussi le grave inconvénient que la résine est exposée à un vieillissement accéléré ainsi qu'à des chocs accidentels pouvant entrainer des fissures.Furthermore, the operation consisting in applying a large thickness of resin around the cylindrical envelope is an operation which is difficult to carry out, which can cause detachments due to shrinkage during its drying. A container thus produced also has the serious drawback that the resin is exposed to accelerated aging as well as to accidental impacts which can cause cracks.

La présente invention vise à pallier tous ces inconvénients.The present invention aims to overcome all these drawbacks.

La présente invention concerne donc un dispositif de protection neutronique recouvrant la paroi externe d'une enveloppe d'un réceptacle enfermant un produit radio-actif, ce dispositif comprenant essentiellement une matière absorbant les neutrons disposée autour de l'enveloppe du réceptacle.The present invention therefore relates to a neutron protection device covering the external wall of an envelope of a receptacle enclosing a radioactive product, this device essentially comprising a neutron absorbing material disposed around the envelope of the receptacle.

Selon une caractéristiqueessentielle de l'invention, ce dispositif comprend en outre une pluralité d'éléments identiques présentant la forme générale de bandes de tôle incurvées, de profil constant sur toute leur longueur, ces bandes étant disposées régulièrement tout autour de l'enveloppe et reliées à elle de façon à ménager des cavités fermées juxtaposées tout autour de l'enveloppe, la matière absorbant les neutrons étant introduite dans lesdites cavités ainsi constituées.According to an essential characteristic of the invention, this device further comprises a plurality of identical elements having the general shape of curved sheet metal strips, of constant profile over their entire length, these strips being regularly arranged all around the envelope and connected to it so as to provide closed cavities juxtaposed all around the envelope, the neutron absorbing material being introduced into said cavities thus formed.

Selon une autre caractéristique de l'invention, chacune de ces bandes de tôle s'étend parallèlement à son enveloppe, a une forme rectangulaire allongée et présente chacune un pliage d'un certain angle selon une ligne parallèle à ses bords latéraux. Ces bandes sont d'autre part disposées les unes à côté des autres autour de l'enveloppe cylindrique, un bord latéral de chaque bande étant relié, sur toute sa longueur, à l'enveloppe cylindrique, et l'autre bord latéral de chaque bande étant relié, sur toute sa longueur, à la bande suivante.According to another characteristic of the invention, each of these sheet metal strips extends parallel to its envelope, has an elongated rectangular shape and each has a folding at a certain angle along a line parallel to its lateral edges. These bands are on the other hand arranged one beside the other around the cylindrical envelope, one lateral edge of each band being connected, over its entire length, to the cylindrical envelope, and the other lateral edge of each band. being connected, over its entire length, to the next strip.

.0- D'autres caractéristiques et avantages de l'invention apparaitront lors de la description détaillée de l'exemple de réalisation qui va suivre, illustré par les dessins annexés.

  • La figure 1 est une vue partielle en coupe radiale d'un conteneur muni d'un dispositif de protection conforme à l'invention.
  • La figure 2 est une vue partielle en coupe longitudinale du même conteneur.
  • La figure 3 est une vue partielle en coupe longitudinale d'une variante du conteneur.
.0- Other features and advantages of the invention will appear during the detailed description of the embodiment which follows, illustrated by the accompanying drawings.
  • Figure 1 is a partial view in radial section of a container provided with a protection device according to the invention.
  • Figure 2 is a partial view in longitudinal section of the same container.
  • Figure 3 is a partial view in longitudinal section of a variant of the container.

En se reportànt à la figure 1, on distingue une enveloppe cylindrique 1 en acier, de forte épaisseur, et qui définit un volume interne cylindrique 2 dans lequel peuvent être disposés des éléments radio-actifs tels que des éléments de combustible nucléaire. L'enveloppe cylindrique 1 est suffisamment épaisse pour éviter la propagation de la plupart des rayonnements radio-actifs ainsi que pour résister mécaniquement à tout choc accidentel envisageable. Sur la face externe 3 de cette enveloppe, sont disposées une série de bandes de soudure par feuillard 5 régulièrement espacées et suivant des génératrices de cette enveloppe cylindrique 1. Tout autour de cette enveloppe cylindrique, sont ensuite disposés des éléments 4, tous identiques, réalisés à partir de tôles en matériau bon conducteur thermique, par exemple en cuivre. Chacun de ces éléments 4 est constitué d'une bande rectangulaire, de longueur sensiblement égale à la longueur de l'enveloppe cylindrique 1. L'un (6) des bords latéraux de chaque bande métallique 4 est soudé en 15 le long d'une bande de soudure par feuillard 5 correspondante ; à partir de ce bord 6, l'élément 4 s'étend vers l'extérieur selon une première partie plane 7 pliée une première fois, longitudinalement, selon une ligne 8, pour être ramené dans un plan circonférentiel, pliée dans l'autre sens selon une seconde ligne 9 parallèle à la ligne 8, puis pliée selon une troisième ligne parallèle 10 de la même manière que le premier pliage 8, de manière que la partie 11 de l'élément soit située circonféren- tiellement. Du fait des trois pliages rapprochés parallèles 8, 9, 10, on donne à l'élément 4 une forme générale de dièdre dont les deux côtés sont constitués par les parties 7 et 11, et, plus précisément, dans la zone commune aux parties 7 et 11, on réalise une rainure 25 de faible dimension en forme, elle aussi, de dièdre. L'élément 4 comporte, d'autre part, un bord latéral 12 soudé à l'élément 4 suivant, ce bord 12 venant s'ajuster dans la rainure 25 réalisée à l'aide du pliage inverse 9. Dans cet exemple particulier de réalisation, la dimension de cette rainure 25, dans la direction radiale, est égale à l'épaisseur de la partie 11 de l'élément de façon que les faces externes 13 des parties périphériques 11 des éléments 4 soient dans le prolongement l'une de l'autre pour constituer une paroi cylindrique parfaite, dépourvue de décrochements. On réalise alors une soudure 14 qui relie le bord 12 d'un élément 4 avec l'élément 4 suivant, en remplissant l'espace restant de la rainure 25, ce qui constitue ainsi une paroi cylindrique externe étanche. Dans cet exemple, les éléments 4 sont réalisés à partir de tôles découpées et pliées, mais on peut aussi les concevoir à partir de matériaux forgés, moulés ou usinés.Referring to Figure 1, there is a cylindrical casing 1 of steel, very thick, and which defines an internal volume cylin drique 2 in which can be placed radioactive elements such as nuclear fuel elements. The cylindrical envelope 1 is thick enough to prevent the propagation of most of the radioactive radiation as well as to mechanically resist any conceivable accidental shock. On the external face 3 of this envelope, are arranged a series of strips of welding by strip 5 regularly spaced and along generatrices of this cylindrical envelope 1. All around this cylindrical envelope, are then arranged elements 4, all identical, made from sheets of material which is a good thermal conductor, for example copper. Each of these elements 4 consists of a rectangular strip, of length substantially equal to the length of the cylindrical envelope 1. One (6) of the lateral edges of each metal strip 4 is welded in 15 along a corresponding strip welding seam 5; from this edge 6, the element 4 extends towards the outside in a first flat part 7 folded a first time, longitudinally, along a line 8, to be brought back in a circumferential plane, folded in the other direction along a second line 9 parallel to line 8, then folded along a third parallel line 10 in the same way as the first fold 8, so that the part 11 of the element is located circumferentially. Due to the three parallel close folds 8, 9, 10, element 4 is given a general dihedral shape, the two sides of which are formed by parts 7 and 11, and, more precisely, in the zone common to parts 7 and 11, a groove 25 of small dimension is produced, also in the form of a dihedral. The element 4 comprises, on the other hand, a lateral edge 12 welded to the next element 4, this edge 12 coming to fit in the groove 25 produced by means of reverse folding 9. In this particular example of embodiment , the dimension of this groove 25, in the radial direction, is equal to the thickness of the part 11 of the element so that the external faces 13 of the peripheral parts 11 of the elements 4 are in the extension one of the 'other to constitute a perfect cylindrical wall, devoid of notches. A weld 14 is then produced which connects the edge 12 of an element 4 with the next element 4, filling the remaining space of the groove 25, which thus constitutes a sealed external cylindrical wall. In this example, the elements 4 are made from cut and folded sheets, but they can also be designed from forged, molded or machined materials.

Pour monter l'ensemble des éléments 4, on commence à souder un premier élément 4 sur l'enveloppe cylindrique 1, ou plus exactement sur la soudure par feuillard 5, puis on soude un élément 4 suivant situé, en faisant référence à la figure 1, à gauche du premier élément 4. On monte ainsi tous les éléments 4 en progressant donc dans le sens contraire des aiguilles d'une montre. Ce montage ressemble en fait à la mise en place successive des tuiles sur une toiture, la dernière tuile posée comprenant un bord reposant sur la charpente de la toiture et son autre bord sur la tuile précédemment posée.To mount all of the elements 4, one begins to weld a first element 4 on the cylindrical casing 1, or more exactly on the welding by strip 5, then a next element 4 is welded located, with reference to FIG. 1, to the left of the first element 4. Thus all the elements 4 are mounted, thus progressing counterclockwise . This assembly actually resembles the successive placement of the tiles on a roof, the last tile installed comprising an edge resting on the roof frame and its other edge on the tile previously laid.

On peut remarquer que les deux soudures 14 et 15 sont faciles à réaliser parce que l'accès n'est pas gêné par d'autres éléments 4. On peut remarquer aussi que, lorsque l'on a soudé à ses deux extrémités 6 et 12 un élément 4, il constitue un espace étanche 16 délimité par la paroi externe 3 de l'enveloppe cylindrique 1, par les faces internes des parties 7 et 11 d'un élément 4, ainsi que par la face externe de la partie 7 de l'élément 4 précédent.It can be noted that the two welds 14 and 15 are easy to make because the access is not hampered by other elements 4. It can also be noted that, when one has welded at its two ends 6 and 12 an element 4, it constitutes a sealed space 16 delimited by the external wall 3 of the cylindrical envelope 1, by the internal faces of the parts 7 and 11 of an element 4, as well as by the external face of the part 7 of the 'element 4 above.

On peut remarquer d'autre part, que l'exécution des soudures 15 et 14 de chaque élément 4 est facile à réaliser parce qu'il n'y a aucun élément 4 qui gêne cette exécution. Un problème se pose toutefois pour le dernier élément 4 que lion doit souder, parce qu'il rejoint le premier élément 4 soudé en début. Pour résoudre ce problème, on dispose un premier élément 41, soudé avant tout autre, qui ressemble aux éléments 4 normaux mais qui est toutefois dépourvu de la partie 11 de ces éléments 4. Lorsque le dernier élément 42, identique à tous les autres éléments 4, est soudé sur l'enveloppe cylindrique 1, cette soudure est possible puisque l'élément 41 laisse un espace libre entre lui et l'élément 42. On peut alors achever la construction de l'ensemble en mettant un élément 43 qui a une forme identique à celle des parties 11 des éléments normaux 4, et qui achève la construction de la paroi cylindrique externe étanche constituée par l'ensemble des parties 11 des éléments 4.On the other hand, it can be noted that the execution of the welds 15 and 14 of each element 4 is easy to carry out because there is no element 4 which hinders this execution. A problem arises, however, for the last element 4 that lion must weld, because it joins the first element 4 welded at the start. To solve this problem, there is a first element 41, welded before any other, which resembles normal elements 4 but which is however devoid of part 11 of these elements 4. When the last element 42, identical to all the other elements 4 , is welded to the cylindrical casing 1, this welding is possible since the element 41 leaves a free space between it and the element 42. We can then complete the construction of the assembly by putting an element 43 which has a shape identical to that of the parts 11 of the normal elements 4, and which completes the construction of the sealed external cylindrical wall constituted by all of the parts 11 of the elements 4.

A ce stade de la construction, onpeut remplir les espaces étanches 16 dont l'accès d'une des deux extrémités est laissé libre, avec une matière absorbant les neutrons, connue en soi.At this stage of construction, the tight spaces 16 can be filled, the access of one of the two ends of which is left free, with a neutron absorbing material, known per se.

On remarque qu'un conteneur comme décrit précédemment est tout particulièrement efficace parce que, tout autour de son enveloppe cylindrique 1, est disposée une matière absorbant les neutrons qui remplit tous les espaces 16 qui sont juxtaposés. La matière absorbant les neutrons constitue donc une couche pratiquement continue tout autour de l'enveloppe cylindrique 1, cette couche est toutefois interrompue par les parties métalliques 7 des éléments 4. Pour cette raison, il est d'ailleurs préconisé, comme représenté en figure 1, de ne pas disposer ces parties 7 exactement radialement, mais de les incliner légèrement d'un certain angle oc par rapport à une direction radiale 17.Note that a container as described above is particularly effective because, all around its cylindrical envelope 1, is arranged a neutron absorbing material which fills all the spaces 16 which are juxtaposed. The neutron absorbing material therefore constitutes a practically continuous layer all around the cylindrical envelope 1, this layer is however interrupted by the metal parts 7 of the elements 4. For this reason, it is moreover recommended, as shown in FIG. 1, not to arrange these parts 7 exactly radially, but to incline them slightly by a certain angle oc relative to a radial direction 17.

Outre ses bonnes qualités de protection contre les radiations, un conteneur conforme à la présente invention est aussi capable d'évacuer efficacement la chaleur produite par les éléments radio-actifs stockés dans la chambre 2. En effet l'enveloppe cylindrique 1 est mise en communication avec la paroi cylindrique externe formée des parties 11 des éléments 4, à l'aide de toutes les parties 7 des éléments 4. On voit par conséquent que la chaleur de l'enveloppe cylindrique 1 peut se transmettre facilement aux parties 7 des éléments 4, puis aux parties 11 de ces éléments 4 qui sont directement en contact avec l'air ambiant. Si l'on évacue par exemple par convexion natuielle la chaleur de la paroi externe formée par les parties 11, on est en mesure d'extraire une grande puissance calorifique de l'enveloppe cylindrique 1. Pour refroidir efficacement cette paroi externe, on peut disposer, sur chaque élément 11, une multitude d'ailettes 18 radiales soudées aux éléments 11. Il est préférable bien sûr, de souder ces ailettes 18 sur les parties 11 avant de procéder au remplissage des cavités 16 avec la matière absorbant les neutrons.In addition to its good radiation protection qualities, a container in accordance with the present invention is also capable of efficiently dissipating the heat produced by the radioactive elements stored in the chamber 2. In fact the cylindrical envelope 1 is placed in communication with the external cylindrical wall formed by the parts 11 of the elements 4, using all the parts 7 of the elements 4. It can therefore be seen that the heat from the cylindrical envelope 1 can be easily transmitted to the parts 7 of the elements 4, then to the parts 11 of these elements 4 which are directly in contact with the ambient air. If, for example, the heat from the external wall formed by the parts 11 is removed by natural convection, it is possible to extract a high calorific power from the cylindrical envelope 1. To effectively cool this external wall, it is possible to have , on each element 11, a multitude of radial fins 18 welded to the elements 11. It is of course preferable to weld these fins 18 on the parts 11 before filling the cavities 16 with the neutron absorbing material.

Comme on peut le voir en figure 2 les cavités longitudinales 16 remplies de matière absorbant les neutrons débouchent aux extrémités dans des cavités annulaires 19, 20 qui sont elles-mêmes remplies de matière absorbant les neutrons, des tôles annulaires 21, 22 reliant de façon étanche les extrémités de la paroi cylindrique 11 et les extrémités 23, 24 de l'enveloppe cylindrique 1. De cette manière, la matière absorbant les neutrons est entièrement enfermée dans une enveloppe étanche, on peut ainsi immerger dans une piscine un tel conteneur en évitant tout risque d'infiltration de l'eau à l'intérieur de la matière absorbant les neutrons. D'autre part, cette matière résiste beaucoup plus longtemps au vieillissement que si elle était exposée à l'air libre.As can be seen in FIG. 2, the longitudinal cavities 16 filled with neutron absorbing material open out at the ends into annular cavities 19, 20 which are themselves filled with neutron absorbing material, annular sheets 21, 22 sealingly connecting the ends of the cylindrical wall 11 and the ends 23, 24 of the cylindrical envelope 1. In this way, the neutron absorbing material is entirely enclosed in a sealed envelope, one can thus immerse in a swimming pool such a container avoiding any risk of water entering the neutron absorbing material. On the other hand, this material resists aging much longer than if it were exposed to the open air.

Les profilés 7 peuvent aussi s'étendre sur toute la longueur du conteneur (comme représenté en figure 3). Dans ce cas, les éléments 21 et 22 n'existent pas, les extrémités 23, 24 de l'enveloppe obturent directement les extrémités des cavités 16.The profiles 7 can also extend over the entire length of the container (as shown in Figure 3). In this case, the elements 21 and 22 do not exist, the ends 23, 24 of the envelope directly close off the ends of the cavities 16.

Il est possible aussi de concevoir les ailettes de refroidissement 18 comme faisant partie intégrante des éléments 4. Pour réaliser cela, il suffit de prévoir pour chaque élément 4 un prolongement radial vers l'extérieur à l'extrémité 12 de ces éléments 4.It is also possible to design the cooling fins 18 as an integral part of the elements 4. To do this, it suffices to provide for each element 4 a radial extension towards the outside at the end 12 of these elements 4.

L'invention ne se limite pas au mode de réalisation qui vient d'être décrit à titre d'exemple, mais elle en comporte au contraire toutes les variantes de réalisation.The invention is not limited to the embodiment which has just been described by way of example, but on the contrary comprises all the variant embodiments thereof.

Claims (9)

1.- Dispositif de protection neutronique recouvrant la paroi externe de l'enveloppe d'un récipient enfermant un produit radio-actif, ce dispositif comprenant essentiellement une matière absorbant les neutrons, disposée autour de l'enveloppe du récipient,
caractérisé par le fait qu'il comprend en outre une pluralité d'éléments identiques (4) présentant chacun la forme générale d'une bande de tôle unique incurvée, de profil constant sur toute sa longueur, ces éléments identiques (4) étant disposés régulièrement tout autour de l'enveloppe (1) et reliés à elle de façon à ménager, tout autour de l'enveloppe (1), des cavités (16) fermées, juxtaposées, dont trois des parois sont constituées par les éléments (4), et que la matière absorbant les neutrons est enfermée dans lesdites cavités ainsi constituées.1.- Neutron protection device covering the external wall of the envelope of a container enclosing a radioactive product, this device essentially comprising a neutron absorbing material, disposed around the envelope of the container,
characterized by the fact that it further comprises a plurality of identical elements (4) each having the general shape of a single curved sheet metal strip, of constant profile over its entire length, these identical elements (4) being arranged regularly all around the envelope (1) and connected to it so as to provide, all around the envelope (1), closed, juxtaposed cavities (16), three of the walls of which are formed by the elements (4), and that the neutron absorbing material is enclosed in said cavities thus formed. 2.- Dispositif de protection neutronique selon la revendication 1,
caractérisé par le fait que chacune de ces bandes-(4) s'étend parallèlement à l'axe de l'enveloppe cylindrique (1), a une forme rectangulaire allongée et présente un pliage d'un certain angle selon une ligne (8) parallèle à ses bords latéraux (6, 12), que ces bandes sont disposées les unes à côté des autres autour de l'enveloppe, qu'un bord latéral (6) de chaque bande (4) est relié, sur toute sa longueur, à l'enveloppe (1), et que l'autre bord latéral (12) de chaque bande (4) est relié, sur toute sa longueur, à la bande (4) suivante, au voisinage de la ligne (8) de pliage de cette bande suivante.2. A neutron protection device according to claim 1,
characterized by the fact that each of these bands (4) extends parallel to the axis of the cylindrical envelope (1), has an elongated rectangular shape and has a folding at a certain angle along a line (8) parallel to its lateral edges (6, 12), that these bands are arranged one beside the other around the envelope, that a lateral edge (6) of each band (4) is connected, over its entire length, to the envelope (1), and that the other lateral edge (12) of each strip (4) is connected, over its entire length, to the next strip (4), in the vicinity of the fold line (8) of this next band. 3.- Dispositif de protection neutronique selon l'une des revendications 1 et 2,
caractérisé par le fait que'les liaisons (15) des bandes (4) avec l'enveloppe cylindrique (1) et les liaisons (14) de ces bandes entre elles sont réalisées par soudage.3.- neutron protection device according to one of claims 1 and 2,
characterized by the fact that the connections (15) of the bands (4) with the cylindrical envelope (1) and the connections (14) of these bands between them are produced by welding. 4.- Dispositif de protection neutronique selon l'une des revendications 1 à 3,
caractérisé par le fait que la matière absorbant les neutrons remplit entièrement les cavités (16) formées à l'aide des bandes (4), et qu'il est prévu en outre des éléments (21, 22) venant s'adapter aux extrémités des bandes (4) et soudés à ces extrémités, pour enfermer de façon étanche la matière absorbant les neutrons à l'intérieur des cavités (16).4.- neutron protection device according to one of claims 1 to 3,
characterized by the fact that the neutron absorbing material completely fills the cavities (16) formed with the aid of the strips (4), and that elements (21, 22) are further provided which adapt to the ends of the strips (4) and welded at these ends, to seal the neutron absorbing material inside the cavities (16). 5.- Dispositif de protection neutronique selon l'une quelconque des revendications 2 à 4, caractérisé par le fait que la partie plane (7) de chaque bande (4) s'étendant entre l'enveloppe cylindrique (1) et la ligne de pliage (8) est inclinée d'un certain angleo( par rapport à la direction radiale (17), de façon que tout rayonnement radio-actif dirigé vers l'extérieur de l'enveloppe (1) rencontre une zone de matière absorbant les neutrons, et que d'autre part, la partie (11) de chaque bande (4) s'étendant entre la ligne de pliage (8) et le bord (12) relié à la bande suivante présente une forme de portion de cylindre, de façon que l'ensemble de toutes ces parties (11) des bandes constitue une paroi cylindrique complète disposée concentriquement autour de l'enveloppe (1), cette paroi constituant un espace annulaire rempli de matière absorbant les neutrons.5.- neutron protection device according to any one of claims 2 to 4, characterized by the fact that the flat part (7) of each strip (4) extending between the cylindrical envelope (1) and the fold line (8) is inclined at a certain angleo (relative to the radial direction (17), so that any radioactive radiation directed towards the outside of the envelope (1) meets a zone of neutron absorbing material, and that on the other hand, the part (11) of each band (4 ) extending between the fold line (8) and the edge (12) connected to the next strip has the shape of a cylinder portion, so that the assembly of all these parts (11) of the strips constitutes a cylindrical wall complete disposed concentrically around the envelope (1), this wall constituting an annular space filled with neutron absorbing material. 6.- Dispositif de protection neutronique selon la revendication 5,
caractérisé par le fait que la face convexe de chaque bande comporte une rainure (25) en forme de dièdre située le long de la ligne de pliage (8) et destinée à recevoir le bord (12) de la bande suivante, de façon que les faces externes (13) des parties (11) des bandes soient dans le prolongement l'une de l'autre afin de constituer une paroi cylindrique étanche, parfaite, dépourvue de décrochements.6. Neutron protection device according to claim 5,
characterized in that the convex face of each strip has a dihedral-shaped groove (25) located along the fold line (8) and intended to receive the edge (12) of the next strip, so that the external faces (13) of the parts (11) of the strips are in the extension of one another in order to constitute a tight, perfect cylindrical wall, devoid of notches. 7.- Dispositif de protection neutronique selon l'une des revendications 5 ou 6,
caractérisé par le fait qu'il est prévu une pluralité de pièces (18) formant ailettes de refroidissement disposées radialement tout autour de la paroi cylindrique externe (11) et fixée ou soudée à elle.7.- neutron protection device according to one of claims 5 or 6,
characterized in that there is provided a plurality of parts (18) forming cooling fins arranged radially around the outer cylindrical wall (11) and fixed or welded thereto. 8.- Dispositif de protection neutronique selon l'une quelconque des revendications 1 à 7,
caractérisé par le fait que lesdits éléments (4), ainsi que les ailettes de refroidissement (18) sont réalisées à partir de tôles en matière bon conducteur thermique, par exemple en cuivre, découpées et pliées.8.- neutron protection device according to any one of claims 1 to 7,
characterized by the fact that said elements (4), as well as the cooling fins (18) are produced from sheets of good thermal conductor material, for example copper, cut and folded. 9.- Dispositif de protection neutronique selon la revendication 8,
caractérisé par le fait que sur la face externe cylindrique (3) de l'enveloppe (1), il est disposé une série de bandes de soudure par feuillard (5) soudées à l'enveloppe (1) par des moyens électriques, ces bandes de soudure (5) étant disposées régulièrement et parallèlement tout autour de l'enveloppe cylindrique (1), en suivant des génératrices de cette enveloppe, et que les éléments (4) sont soudés en (15) sur ces bandes de soudure (5).9.- neutron protection device according to claim 8,
characterized by the fact that on the cylindrical external face (3) of the envelope (1), there is arranged a series of strips of strip welding (5) welded to the envelope (1) by electrical means, these bands of welding (5) being arranged regularly and parallel all around the cylindrical envelope (1), following generatrices of this envelope, and that the elements (4) are welded at (15) on these weld strips (5) .
EP83400285A 1982-02-12 1983-02-10 Neutron shielding device for radio-active material Expired EP0087350B1 (en)

Priority Applications (1)

Application Number Priority Date Filing Date Title
AT83400285T ATE19560T1 (en) 1982-02-12 1983-02-10 DEVICE FOR NEUTRON PROTECTION FOR A RADIOACTIVE PRODUCT.

Applications Claiming Priority (2)

Application Number Priority Date Filing Date Title
FR8202300A FR2521764A1 (en) 1982-02-12 1982-02-12 NEUTRON PROTECTION DEVICE FOR RADIO-ACTIVE PRODUCT
FR8202300 1982-02-12

Publications (2)

Publication Number Publication Date
EP0087350A1 true EP0087350A1 (en) 1983-08-31
EP0087350B1 EP0087350B1 (en) 1986-04-30

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EP83400285A Expired EP0087350B1 (en) 1982-02-12 1983-02-10 Neutron shielding device for radio-active material

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EP (1) EP0087350B1 (en)
JP (1) JPS58202899A (en)
AT (1) ATE19560T1 (en)
DE (1) DE3363237D1 (en)
FR (1) FR2521764A1 (en)

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* Cited by examiner, † Cited by third party
Publication number Priority date Publication date Assignee Title
EP0343410A2 (en) * 1988-05-24 1989-11-29 Westinghouse Electric Corporation Shipping cask for nuclear fuel
US4896046A (en) * 1988-05-24 1990-01-23 Westinghouse Electric Corp. Fuel rod shipping cask having peripheral fins
US4997618A (en) * 1988-05-24 1991-03-05 Westinghouse Electric Corp. Fuel rod shipping cask having peripheral fins
EP0942435A1 (en) * 1998-03-13 1999-09-15 Societe Pour Les Transports De L'industrie Nucleaire Transnucleaire Radiation screening arrangement for radioactive material transport container
EP1008994A1 (en) * 1998-12-09 2000-06-14 GNB Gesellschaft für Nuklear-Behälter mbH Shielded container
EP1355320A1 (en) * 2001-01-25 2003-10-22 Mitsubishi Heavy Industries, Ltd. Cask and production method for cask
EP1524673A1 (en) * 2002-07-23 2005-04-20 Mitsubishi Heavy Industries, Ltd. Cask and method of producing the same
FR2974228A1 (en) * 2011-04-18 2012-10-19 Tn Int THERMAL CONDUCTION ELEMENT FOR IMPROVING THE MANUFACTURE OF A TRANSPORT AND / OR STORAGE PACKAGING OF RADIOACTIVE MATERIALS
WO2017064174A1 (en) * 2015-10-16 2017-04-20 Tn International Cooling element with base for discharging heat from a package
WO2017167853A1 (en) * 2016-04-01 2017-10-05 Tn International Transport and/or storage packaging for radioactive materials equipped with heat dissipation devices produced in one piece

Families Citing this family (4)

* Cited by examiner, † Cited by third party
Publication number Priority date Publication date Assignee Title
JPS59182396A (en) * 1983-03-31 1984-10-17 三井造船株式会社 Method of making cask for spent nuclear fuel
JPS59182397A (en) * 1983-03-31 1984-10-17 三井造船株式会社 Method of making cask for spent nuclear
JPWO2002025670A1 (en) * 2000-09-20 2004-01-29 株式会社日立製作所 Nuclear fuel transport container
JP2020012761A (en) * 2018-07-19 2020-01-23 株式会社神戸製鋼所 Method for manufacturing radioactive material transportation storage container

Citations (5)

* Cited by examiner, † Cited by third party
Publication number Priority date Publication date Assignee Title
US3780306A (en) * 1971-05-27 1973-12-18 Nat Lead Co Radioactive shipping container with neutron and gamma absorbers
DE2817193A1 (en) * 1978-04-20 1979-10-31 Transnuklear Gmbh Transport casket for irradiated fuel elements - with webs in concrete filling between inner and outer metal shell
GB2033287A (en) * 1978-10-17 1980-05-21 Transnuklear Gmbh Shielding container for transporting and/or storing burnt-up nuclear fuel elements
FR2454157A1 (en) * 1979-04-14 1980-11-07 Transnuklear Gmbh SHIELDED CONTAINER FOR TRANSPORTING AND / OR STORING BURNED NUCLEAR FUEL ELEMENTS
FR2471027A1 (en) * 1979-11-17 1981-06-12 Transnuklear Gmbh TRANSPORT AND / OR STORAGE VASE FOR RADIOACTIVE MATERIALS

Family Cites Families (2)

* Cited by examiner, † Cited by third party
Publication number Priority date Publication date Assignee Title
BE791334A (en) * 1971-11-15 1973-03-01 Lemer & Cie PERFECTED DEVICE FOR AIR COOLING OF RADIOACTIVE PRODUCTS TRANSPORT CASTLES
FR2208165B1 (en) * 1972-11-28 1975-09-12 Robatel Slpi

Patent Citations (5)

* Cited by examiner, † Cited by third party
Publication number Priority date Publication date Assignee Title
US3780306A (en) * 1971-05-27 1973-12-18 Nat Lead Co Radioactive shipping container with neutron and gamma absorbers
DE2817193A1 (en) * 1978-04-20 1979-10-31 Transnuklear Gmbh Transport casket for irradiated fuel elements - with webs in concrete filling between inner and outer metal shell
GB2033287A (en) * 1978-10-17 1980-05-21 Transnuklear Gmbh Shielding container for transporting and/or storing burnt-up nuclear fuel elements
FR2454157A1 (en) * 1979-04-14 1980-11-07 Transnuklear Gmbh SHIELDED CONTAINER FOR TRANSPORTING AND / OR STORING BURNED NUCLEAR FUEL ELEMENTS
FR2471027A1 (en) * 1979-11-17 1981-06-12 Transnuklear Gmbh TRANSPORT AND / OR STORAGE VASE FOR RADIOACTIVE MATERIALS

Cited By (20)

* Cited by examiner, † Cited by third party
Publication number Priority date Publication date Assignee Title
EP0343410A2 (en) * 1988-05-24 1989-11-29 Westinghouse Electric Corporation Shipping cask for nuclear fuel
US4896046A (en) * 1988-05-24 1990-01-23 Westinghouse Electric Corp. Fuel rod shipping cask having peripheral fins
EP0343410A3 (en) * 1988-05-24 1990-05-16 Westinghouse Electric Corporation Shipping cask for nuclear fuel
US4997618A (en) * 1988-05-24 1991-03-05 Westinghouse Electric Corp. Fuel rod shipping cask having peripheral fins
EP0942435A1 (en) * 1998-03-13 1999-09-15 Societe Pour Les Transports De L'industrie Nucleaire Transnucleaire Radiation screening arrangement for radioactive material transport container
FR2776118A1 (en) * 1998-03-13 1999-09-17 Transnucleaire RADIATION PROTECTION DEVICE FOR CONTAINER FOR TRANSPORTING RADIOACTIVE MATERIAL
US6195404B1 (en) 1998-03-13 2001-02-27 Societe Pour Les Transports De L'industrie Nucleaire - Transnucleaire Anti-radiation device for containers used to ship radioactive materials
EP1008994A1 (en) * 1998-12-09 2000-06-14 GNB Gesellschaft für Nuklear-Behälter mbH Shielded container
EP1355320A1 (en) * 2001-01-25 2003-10-22 Mitsubishi Heavy Industries, Ltd. Cask and production method for cask
EP1355320A4 (en) * 2001-01-25 2010-01-06 Mitsubishi Heavy Ind Ltd Cask and production method for cask
EP1524673A4 (en) * 2002-07-23 2007-08-08 Mitsubishi Heavy Ind Ltd Cask and method of producing the same
EP1524673A1 (en) * 2002-07-23 2005-04-20 Mitsubishi Heavy Industries, Ltd. Cask and method of producing the same
FR2974228A1 (en) * 2011-04-18 2012-10-19 Tn Int THERMAL CONDUCTION ELEMENT FOR IMPROVING THE MANUFACTURE OF A TRANSPORT AND / OR STORAGE PACKAGING OF RADIOACTIVE MATERIALS
WO2012143224A1 (en) * 2011-04-18 2012-10-26 Tn International Thermally conductive element enabling an improvement in the manufacture of packaging for the transport and/or storage of radioactive material
US9040946B2 (en) 2011-04-18 2015-05-26 Tn International Thermal-conduction element for improving the manufacture of a package for transporting and/or storing radioactive materials
WO2017064174A1 (en) * 2015-10-16 2017-04-20 Tn International Cooling element with base for discharging heat from a package
FR3042635A1 (en) * 2015-10-16 2017-04-21 Tn Int COOLING ELEMENT WITH EMBASE FOR DISCHARGING HEAT FROM A PACKAGING
US10522260B2 (en) 2015-10-16 2019-12-31 Tn International Cooling element with base for discharging heat from a package
WO2017167853A1 (en) * 2016-04-01 2017-10-05 Tn International Transport and/or storage packaging for radioactive materials equipped with heat dissipation devices produced in one piece
FR3049756A1 (en) * 2016-04-01 2017-10-06 Tn Int PACKAGING OF TRANSPORT AND / OR STORAGE OF RADIOACTIVE MATERIALS EQUIPPED WITH HEAT DISSIPATION DEVICES MADE OF A SINGLE PURPOSE

Also Published As

Publication number Publication date
FR2521764A1 (en) 1983-08-19
JPH0225478B2 (en) 1990-06-04
EP0087350B1 (en) 1986-04-30
JPS58202899A (en) 1983-11-26
DE3363237D1 (en) 1986-06-05
FR2521764B1 (en) 1985-03-01
ATE19560T1 (en) 1986-05-15

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