EP0087350B1 - Einrichtung zum Neutronenschutz für ein radioaktives Produkt - Google Patents

Einrichtung zum Neutronenschutz für ein radioaktives Produkt Download PDF

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Publication number
EP0087350B1
EP0087350B1 EP83400285A EP83400285A EP0087350B1 EP 0087350 B1 EP0087350 B1 EP 0087350B1 EP 83400285 A EP83400285 A EP 83400285A EP 83400285 A EP83400285 A EP 83400285A EP 0087350 B1 EP0087350 B1 EP 0087350B1
Authority
EP
European Patent Office
Prior art keywords
enclosure
neutron
strip
members
strips
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.)
Expired
Application number
EP83400285A
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English (en)
French (fr)
Other versions
EP0087350A1 (de
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
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 Creusot Loire SA, Framatome SA filed Critical Creusot Loire SA
Priority to AT83400285T priority Critical patent/ATE19560T1/de
Publication of EP0087350A1 publication Critical patent/EP0087350A1/de
Application granted granted Critical
Publication of EP0087350B1 publication Critical patent/EP0087350B1/de
Expired 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
    • 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.
  • Patent FR-A-2,179,672 describes a neutron protection device covering the external wall of the envelope of a container enclosing a radioactive product, this device comprising a neutron absorbing material, disposed around the envelope of the container and a plurality of identical elements each having the general shape of a strip of curved sheet metal, of constant profile over its entire length, these identical elements being regularly arranged all around the envelope. These elements provide, all around the envelope, juxtaposed cavities in which the neutron absorbing material is enclosed. However, for each cavity, only two of the four walls parallel to the axis of the device are formed by said elements, the other two walls being formed on the one hand by said envelope and on the other hand by an outer shell.
  • the present invention overcomes these drawbacks.
  • the present invention relates to a 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 and a plurality of elements.
  • identical qi have the general shape of a single sheet metal strip extending along its largest dimension along the generatrices of the container shell and whose cross section has a constant curved profile over its entire length, said identical elements being regularly arranged all around and in radial directions relative to the axis of symmetry of the container shell and having one of their edges taken along the largest dimension of the sheet metal strips directly connected to the envelope.
  • each element is connected to the next element and the elements are connected to the envelope so as to provide, all around the envelope, closed, juxtaposed cavities, including three of the four walls parallel to the axis of the device are constituted by two elements and the fourth of which is constituted by the envelope, and the neutron absorbing material is enclosed in 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 strips are on the other hand arranged side by side around the cylindrical envelope, one lateral edge of each strip being connected, over its entire length, to the cylindrical envelope, and the other lateral edge of each strip being connected, over its entire length, to the next strip.
  • FIG. 1 there is a cylindrical envelope 1 of steel, very thick, and which defines a cylindrical internal volume 2 in which can be arranged 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 manner as the first folding 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 of 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 sealed 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 conti bare 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 place these parts 7 exactly radially , but to tilt them slightly at a certain angle a with respect 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 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 achieve this, it suffices to provide for each element 4 a radial extension towards the outside at the end 12 of these elements 4.

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  • Physics & Mathematics (AREA)
  • Engineering & Computer Science (AREA)
  • General Engineering & Computer Science (AREA)
  • High Energy & Nuclear Physics (AREA)
  • Particle Accelerators (AREA)
  • Shielding Devices Or Components To Electric Or Magnetic Fields (AREA)
  • Butt Welding And Welding Of Specific Article (AREA)
  • Analysing Materials By The Use Of Radiation (AREA)
  • Monitoring And Testing Of Nuclear Reactors (AREA)
  • Measurement Of Radiation (AREA)
  • Emergency Protection Circuit Devices (AREA)

Claims (9)

1. Neutronenschutzvorrichtung, die die Außenwand der Hülle eines Behälters bedeckt, der ein radioaktives Material einschließt und die im wesentlichen aufweist:
- ein neutronenabsorbierendes Material, das um die Hülle des Behälters herum angeordnet ist und
- mehrere identische Elemente (4), die allgemein die Form eines einstückigen Blechbandes haben, das sich mit seiner längeren Seite längs den Erzeugenden der Hülle des Behälters erstreckt und dessen Querschnitt auf seiner gesamten Länge ein gekrümmtes Profil aufweist, wobei die identischen Elemente gleichmäßig um die Hülle herum und in Radialrichtungen bezüglich der Symmetrieachse der Hülle des Behälters angeordnet sind und wobei einer ihrer Ränder an den Längsseiten der Blechbänder direkt mit der Hülle verbunden ist,
dadurch gekennzeichnet, daß jedes Element (4) mit dem darauffolgenden Element (4) verbunden ist und daß die Elemente (4) derart mit der Hülle (1) verbunden sind, daß rings um die Hülle (1) herum geschlossene Hohlräume (16) gebildet werden, die nebeneinandergeordnet sind und von denen drei ihrer vier zu der Achse der Vorrichtung parallelen Seitenflächen aus zwei Elementen (4) bestehen und deren vierte Seitenwand von der Hülle (1) gebildet wird und dadurch, daß das neutronenabsorbierende Material in den so gebildeten Hohlräumen (16) eingeschlossen ist.
2. Einrichtung nach Anspruch 1, dadurch gekennzeichnet, daß jedes der Bänder (4), die sich parallel zur Achse der zylinderförmigen Hülle (1) erstrecken, die Form eines länglichen Rechtecks hat und eine Knickfalte unter einem bestimmten Winkel längs einer zu den Seitenrändern parallelen Linie (8) aufweist, daß diese Bänder nebeneinander um die Hülle herum angeordnet sind, daß ein Seitenrand (6) eines jeden Bandes (4) über seine gesamte Länge mit der Hülle (1) verbunden ist und dadurch, daß der andere Seitenrand (12) eines jeden Bandes über seine gesamte Länge mit dem darauffolgenden Band (4), in der Nähe der Faltlinie (8) dieses nächsten Bandes verbunden ist.
3. Einrichtung nach Anspruch 1 oder 2, dadurch gekennzeichnet, daß die Verbindungen (15) der Bänder (4) mit der zylindrischen Hülle (1) und die Verbindung (14) dieser Bänder untereinander durch Verschweißungen gebildet sind.
4. Einrichtung nach einem der Ansprüche 1 bis 3, dadurch gekennzeichnet, daß das neutronenabsorbierende Material die mittels der Bänder (4) gebildeten Hohlräume (16) vollständig ausfüllt und dadurch, daß außerdem Elemente (21, 22) vorgesehen sind, die an die Enden der Bänder (4) angepaßt und dort verschweißt werden, um das neutronenabsorbierende Material im Inneren der Hohlräume (16) dicht einzuschließen.
5. Einrichtung nach einem der Ansprüche 2 bis 4, dadurch gekennzeichnet, daß der ebene Teil (7) eines jeden Bandes (4), der sich zwischen der zylindrischen Hülle (1) und der Faltlinie (8) befindet, um einen bestimmten Winkel a im Verhältnis zu der Radialrichtung (17) geneigt ist, derart, daß alle radioaktiven Strahlen, die zum Äußeren der Hülle (1) hin gelenkt werden in einen Bereich mit neutronenabsorbierendem Material gelangen, und daß andererseits der Teil (11) eines jeden Bandes (4), der sich zwischen der Faltlinie (8) und dem Rand (12), der mit dem folgenden Band verbunden ist, erstreckt, die Form eines Zylinderschnitts aufweist, derart, daß die Gesamtheit aller dieser Teile (11) der Bänder eine zylinderförmige Wandung bildet, die vollständig konzentrisch um die Hülle (1) herum angeordnet ist, wobei diese Wandung einen mit neutronenabsorbierendem Material gefüllten Ringraum bildet.
6. Einrichtung nach Anspruch 5, dadurch gekennzeichnet, daß die konvexe Seite eines jeden-Bandes eine Nut (5) in Form eines Dieders aufweist, die entlang der Faltlinie (8) angeordnet ist und dazu bestimmt ist, den Rand (12) des darauffolgenden Bandes aufzunehmen, derart, daß die Außenseiten (13) der Teile (11) der Bänder jeweils in der Verlängerung des nächsten Bandes liegen, um so eine perfekte, dichte ununterbrochene zylinderförmige Wandung zu bilden.
7. Einrichtung nach einem der Ansprüche 5 oder 6, dadurch gekennzeichnet, daß mehrere Stücke (18) vorgesehen sind, die Kühlrippen bilden und radial um die gesamte zylindrische Außenwand (11) herum angeordnet und an dieser angeschweißt sind.
8. Einrichtung nach einem der Ansprüche 1 bis 7, dadurch gekennzeichnet, daß die Elemente (4) sowie die Kühlrippen (18) aus Blechen aus einem thermisch gut leitendem Material, z. B. Kupfer hergestellt sind, wobei die Elemente aus den Blechen ausgeschnitten und gefaltet sind.
9. Einrichtung nach Anspruch 8, dadurch gekennzeichnet, daß auf der zylindrischen Außenseite (3) der Hülle (1) eine Reihe von Schweißbändern in Form von Blättern (5) angeordnet sind, die elektrisch an die Hülle (1) angeschweißt sind, wobei die Schweißbander (5) gleichmäßig und parallel zueinander um die Zylinderhülle (1) entlang der Erzeugenden dieser Hülle angeordnet sind und dadurch, daß die Elemente (4) an den Stellen (15) auf diesen Schweißbändern (5) angeschweißt sind.
EP83400285A 1982-02-12 1983-02-10 Einrichtung zum Neutronenschutz für ein radioaktives Produkt Expired EP0087350B1 (de)

Priority Applications (1)

Application Number Priority Date Filing Date Title
AT83400285T ATE19560T1 (de) 1982-02-12 1983-02-10 Einrichtung zum neutronenschutz fuer ein radioaktives produkt.

Applications Claiming Priority (2)

Application Number Priority Date Filing Date Title
FR8202300A FR2521764A1 (fr) 1982-02-12 1982-02-12 Dispositif de protection neutronique pour produit radio-actif
FR8202300 1982-02-12

Publications (2)

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

Family

ID=9270925

Family Applications (1)

Application Number Title Priority Date Filing Date
EP83400285A Expired EP0087350B1 (de) 1982-02-12 1983-02-10 Einrichtung zum Neutronenschutz für ein radioaktives Produkt

Country Status (5)

Country Link
EP (1) EP0087350B1 (de)
JP (1) JPS58202899A (de)
AT (1) ATE19560T1 (de)
DE (1) DE3363237D1 (de)
FR (1) FR2521764A1 (de)

Cited By (2)

* Cited by examiner, † Cited by third party
Publication number Priority date Publication date Assignee Title
DE19856685A1 (de) * 1998-12-09 2000-06-15 Gnb Gmbh Abschirmbehälter
KR20140007921A (ko) * 2011-04-18 2014-01-20 티엔 인터내셔날 방사능 재료의 운반 및/또는 저장용 패키지의 제작을 개선시킴을 가능하게 하는 열전도성 요소

Families Citing this family (12)

* Cited by examiner, † Cited by third party
Publication number Priority date Publication date Assignee Title
JPS59182396A (ja) * 1983-03-31 1984-10-17 三井造船株式会社 使用済核燃料輸送容器の製造方法
JPS59182397A (ja) * 1983-03-31 1984-10-17 三井造船株式会社 使用済核燃料輸送容器の製造方法
US4997618A (en) * 1988-05-24 1991-03-05 Westinghouse Electric Corp. Fuel rod shipping cask having peripheral fins
US4896046A (en) * 1988-05-24 1990-01-23 Westinghouse Electric Corp. Fuel rod shipping cask having peripheral fins
EP0343410A3 (de) * 1988-05-24 1990-05-16 Westinghouse Electric Corporation Transportbehälter für Kernbrennstoff
FR2776118B1 (fr) * 1998-03-13 2000-06-09 Transnucleaire Dispositif de protection contre les rayonnements pour conteneur de transport de matieres radioactives
JP3416657B2 (ja) * 2001-01-25 2003-06-16 三菱重工業株式会社 キャスクおよびキャスクの製造方法
JPWO2002025670A1 (ja) * 2000-09-20 2004-01-29 株式会社日立製作所 核燃料輸送容器
JP3978210B2 (ja) * 2002-07-23 2007-09-19 三菱重工業株式会社 キャスク
FR3042635B1 (fr) * 2015-10-16 2017-12-15 Tn Int Element de refroidissement avec embase pour evacuer de la chaleur d'un emballage
FR3049756B1 (fr) * 2016-04-01 2020-06-12 Tn International Emballage de transport et/ou d'entreposage de matieres radioactives equipe de dispositifs de dissipation de chaleur realises d'un seul tenant
JP2020012761A (ja) * 2018-07-19 2020-01-23 株式会社神戸製鋼所 放射性物質輸送貯蔵容器の製造方法

Family Cites Families (7)

* 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
BE791334A (fr) * 1971-11-15 1973-03-01 Lemer & Cie Dispositif perfectionne pour le refroidissement par air de chateau de transport de produits radioactifs
FR2208165B1 (de) * 1972-11-28 1975-09-12 Robatel Slpi
DE2817193A1 (de) * 1978-04-20 1979-10-31 Transnuklear Gmbh Abschirmbehaelter fuer den transport und die lagerung bestrahlter brennelemente
DE2845129A1 (de) * 1978-10-17 1980-04-30 Transnuklear Gmbh Abschirmbehaelter mit neutronenabschirmung fuer den transport und/oder die lagerung abgebrannter brennelemente
DE7911030U1 (de) * 1979-04-14 1979-08-23 Transnuklear Gmbh, 6450 Hanau Abschirmbehaelter zum transport und/ oder zur lagerung abgebrannter brennelemente
DE7932527U1 (de) * 1979-11-17 1980-04-24 Transnuklear Gmbh, 6450 Hanau Transport- und/oder lagerbehaelter fuer radioaktive stoffe

Cited By (3)

* Cited by examiner, † Cited by third party
Publication number Priority date Publication date Assignee Title
DE19856685A1 (de) * 1998-12-09 2000-06-15 Gnb Gmbh Abschirmbehälter
KR20140007921A (ko) * 2011-04-18 2014-01-20 티엔 인터내셔날 방사능 재료의 운반 및/또는 저장용 패키지의 제작을 개선시킴을 가능하게 하는 열전도성 요소
KR101996318B1 (ko) 2011-04-18 2019-07-04 티엔 인터내셔날 방사능 재료의 운반 및/또는 저장용 패키지의 제작을 개선시킴을 가능하게 하는 열전도성 요소

Also Published As

Publication number Publication date
JPS58202899A (ja) 1983-11-26
JPH0225478B2 (de) 1990-06-04
FR2521764A1 (fr) 1983-08-19
ATE19560T1 (de) 1986-05-15
DE3363237D1 (en) 1986-06-05
EP0087350A1 (de) 1983-08-31
FR2521764B1 (de) 1985-03-01

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