EP1008994A1 - Shielded container - Google Patents

Shielded container Download PDF

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Publication number
EP1008994A1
EP1008994A1 EP99120210A EP99120210A EP1008994A1 EP 1008994 A1 EP1008994 A1 EP 1008994A1 EP 99120210 A EP99120210 A EP 99120210A EP 99120210 A EP99120210 A EP 99120210A EP 1008994 A1 EP1008994 A1 EP 1008994A1
Authority
EP
European Patent Office
Prior art keywords
longitudinal
longitudinal chambers
shielding
chambers
container according
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
EP99120210A
Other languages
German (de)
French (fr)
Other versions
EP1008994B1 (en
Inventor
Harry Dr.-Ing. Spilker
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.)
GNB Gesellschaft fuer Nuklear Behaelter mbH
Original Assignee
GNB Gesellschaft fuer Nuklear Behaelter mbH
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 GNB Gesellschaft fuer Nuklear Behaelter mbH filed Critical GNB Gesellschaft fuer Nuklear Behaelter mbH
Publication of EP1008994A1 publication Critical patent/EP1008994A1/en
Application granted granted Critical
Publication of EP1008994B1 publication Critical patent/EP1008994B1/en
Anticipated expiration legal-status Critical
Expired - Lifetime 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
    • 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 invention relates to a shielding container made of metal, especially steel, for the transport and storage of spent nuclear reactor fuel elements and the like, with a container jacket with neutron moderator on the outside filled, by welded segment sheets has closed longitudinal chambers.
  • the invention has for its object a shielding container of the type mentioned in such a way that he is easy to manufacture and reliable.
  • the solution to this problem according to the invention consists in that the longitudinal chambers at an obtuse angle to the radial A moderator overlap in the direction and in the radial direction worked out producing from the container jacket are.
  • the oblique arrangement of the longitudinal chambers is an optimal one Setting the shielding properties from physical Reasons possible.
  • the gamma shielding is close at the source and the neutron shield on the outer edge of the Gamma shielding.
  • By tilting the built-in Neutron moderator neutron streaming is excluded, because the moderator webs overlap in the radial direction.
  • the heat conduction is through the webs of the container base material achieved sufficiently.
  • the longitudinal chambers are preferably made of the container jacket milled out. It is recommended to use the longitudinal chambers to be carried out with ends tapering in the longitudinal direction.
  • the longitudinal chambers should go through several, preferably four longitudinal chambers extending segment plates closed his. In this context, it is recommended the segment sheets in the longitudinal direction between the longitudinal chambers extending webs and in the circumferential direction below the lower and above the upper ends to weld on. Otherwise, the segment sheets should be in front welding on the outside with welded on Longitudinal cooling fins are provided, so that a later attachment on the shielding container is avoided.
  • the shielding container shown in the figures exists Made of metal, especially steel, and is for transportation and the storage of spent nuclear reactor fuel elements or similar radioactive objects.
  • its basic structure consists of a a bottom 1 provided container jacket 2, on the one (not shown) lid can be placed.
  • the container jacket 2 has on its outside Longitudinal chambers 3, which are filled with neutron moderator 4 and are closed by welded-on segment sheets 5. These longitudinal chambers 3 are, as you can easily see from the figures takes, at an obtuse angle to the radial direction R running and in the radial direction R a moderator coverage milled out of the container jacket 2 generating.
  • the longitudinal chambers 3 end in the longitudinal direction Ends 6 (see Fig. 2).
  • the longitudinal chambers 3 are inherently four longitudinal chambers 3 extending segment sheets 5 closed in the longitudinal direction to webs 7 running between the longitudinal chambers (see Fig. 1) and in the circumferential direction below the lower and welded above the upper ends 6 are. (see Fig. 2). Otherwise you can see the figures without further ado that the segment sheets 5 longitudinal cooling fins welded onto the outside 8 exhibit.

Abstract

The longitudinal chambers (3) run in an obtuse angle to a radial direction (R) and are made of jacket material (2) in the radial direction (R) of a moderator covering. Shielded container made of metal, particularly steel has an outer wall jacket (2) having longitudinal chamber (3) closed by segments of sheet metal and filled with neutron moderator (4) in its outer side.

Description

Die Erfindung betrifft einen Abschirmbehälter aus Metall, insbesondere Stahl, für den Transport und die Lagerung von abgebrannten Kernreaktorbrennelementen und dergleichen, mit einem Behältermantel, der an seiner Außenseite mit Neutronenmoderator gefüllte, durch aufgeschweißte Segmentbleche verschlossene Längskammern aufweist.The invention relates to a shielding container made of metal, especially steel, for the transport and storage of spent nuclear reactor fuel elements and the like, with a container jacket with neutron moderator on the outside filled, by welded segment sheets has closed longitudinal chambers.

Bei einem aus der Praxis bekannten Abschirmbehälter dieser Art sind die Längskammern für den Neutronenmoderator durch auf den Behältermantel aufgeschweißte Radialstege gebildet. Das ist aufwendig und in funktioneller Hinsicht nicht befriedigend. Über die Kammerstege muß die gesamte im Abschirmbehälter entstehende Wärme durch Wärmeleitung an die Oberfläche abgeleitet werden. Gammastrahlung soll durch das Metall des Behältermantels und Neutronenstrahlung durch den Neutronenmoderator abgeschirmt werden. Sind die Radialstege zu dünn, entsteht ein Wärmestau und damit zu hohe Innentemperaturen im Abschirmbehälter. Sind die Radialstege zu dick, entsteht wegen des dort fehlenden Neutronenmoderators ein sogenanntes Neutronenstreaming, d. h. eine erhöhte Dosisleistung durch Neutronen an der Oberfläche. Die Dicke der Radialstege beinhaltet mithin immer einen Kompromiß.In a shielding container known from practice this Art are the longitudinal chambers for the neutron moderator through radial webs welded onto the container jacket. This is complex and not satisfactory from a functional point of view. The entire must be in the shielding container over the chamber webs heat generated by heat conduction to the Surface can be derived. Gamma radiation is said to Metal of the container shell and neutron radiation through the Neutron moderator are shielded. Are the radial webs If it is too thin, heat builds up and the internal temperatures are too high in the shielding container. Are the radial webs too thick, arises because of the missing neutron moderator so-called neutron streaming, i.e. H. an increased Dose output by neutrons on the surface. The fat the radial webs therefore always involve a compromise.

Der Erfindung liegt die Aufgabe zugrunde, einen Abschirmbehälter der eingangs genannten Art so auszubilden, daß er einfach herstellbar und funktionssicher ist.The invention has for its object a shielding container of the type mentioned in such a way that he is easy to manufacture and reliable.

Die erfindungsgemäße Lösung dieser Aufgabe besteht darin, daß die Längskammern in einem stumpfen Winkel zur radialen Richtung verlaufend und in radialer Richtung eine Moderatorüberdeckung erzeugend aus dem Behältermantel herausgearbeitet sind.The solution to this problem according to the invention consists in that the longitudinal chambers at an obtuse angle to the radial A moderator overlap in the direction and in the radial direction worked out producing from the container jacket are.

Durch die schräge Anordnung der Längskammern wird eine optimale Einstellung der Abschirmeigenschaften aus physikalischen Gründen möglich. Die Gammaabschirmung erfolgt nah an der Quelle und die Neutronenabschirmung am Außenrand der Gammaabschirmung. Durch die Schrägstellung des eingebauten Neutronenmoderators ist ein Neutronenstreaming ausgeschlossen, da sich die Moderatorstege in radialer Richtung überdecken. Die Wärmeleitung wird durch die Stege des Behältergrundmaterials in ausreichender Weise erreicht.The oblique arrangement of the longitudinal chambers is an optimal one Setting the shielding properties from physical Reasons possible. The gamma shielding is close at the source and the neutron shield on the outer edge of the Gamma shielding. By tilting the built-in Neutron moderator, neutron streaming is excluded, because the moderator webs overlap in the radial direction. The heat conduction is through the webs of the container base material achieved sufficiently.

Für die weitere Ausgestaltung bestehen im Rahmen der Erfindung mehrere Möglichkeiten, deren bevorzugte nachfolgend aufgeführt sind:For the further embodiment there are within the scope of the invention several options, their preferred below are listed:

So sind die Längskammern vorzugsweise aus dem Behältermantel herausgefräst. Dabei empfiehlt es sich, die Längskammern mit in Längsrichtung auslaufenden Enden auszuführen. Die Längskammern sollten durch sich über mehrere, vorzugsweise vier Längskammern erstreckende Segmentbleche verschlossen sein. In diesem Zusammenhang empfiehlt es sich, die Segmentbleche in Längsrichtung auf zwischen den Längskammern verlaufende Stege und in Umfangsrichtung unterhalb der unteren sowie oberhalb der oberen auslaufenden Enden aufzuschweißen. Im übrigen sollten die Segmentbleche vor dem Aufschweißen auf ihrer Außenseite mit aufgeschweißten Längskühlrippen versehen werden, so daß eine spätere Anbringung am Abschirmbehälter vermieden wird. The longitudinal chambers are preferably made of the container jacket milled out. It is recommended to use the longitudinal chambers to be carried out with ends tapering in the longitudinal direction. The longitudinal chambers should go through several, preferably four longitudinal chambers extending segment plates closed his. In this context, it is recommended the segment sheets in the longitudinal direction between the longitudinal chambers extending webs and in the circumferential direction below the lower and above the upper ends to weld on. Otherwise, the segment sheets should be in front welding on the outside with welded on Longitudinal cooling fins are provided, so that a later attachment on the shielding container is avoided.

Im folgenden wird die Erfindung anhand einer schematisch ein Ausführungsbeispiel darstellenden Zeichnung näher erläutert. Es zeigen

Fig. 1
einen Teil eines Abschirmbehälters im Querschnitt und
Fig. 2
den Gegenstand der Fig. 1 in einem Längsschnitt.
The invention is explained in more detail below with reference to a drawing schematically illustrating an exemplary embodiment. Show it
Fig. 1
part of a shielding container in cross section and
Fig. 2
1 in a longitudinal section.

Der in den Figuren dargestellte Abschirmbehälter besteht aus Metall, insbesondere Stahl und ist für den Transport und die Lagerung von abgebrannten Kernreaktorbrennelementen oder dergleichen radioaktiven Gegenständen bestimmt. In seinem grundsätzlichen Aufbau besteht er aus einem mit einem Boden 1 versehenen Behältermantel 2, auf den ein (nicht dargestellter) Deckel aufsetzbar ist.The shielding container shown in the figures exists Made of metal, especially steel, and is for transportation and the storage of spent nuclear reactor fuel elements or similar radioactive objects. In its basic structure consists of a a bottom 1 provided container jacket 2, on the one (not shown) lid can be placed.

Der Behältermantel 2 verfügt an seiner Außenseite über Längskammern 3, die mit Neutronenmoderator 4 gefüllt sind und durch aufgeschweißte Segmentbleche 5 verschlossen sind. Diese Längskammern 3 sind, wie man unschwer aus den Figuren entnimmt, in einem stumpfen Winkel zur radialen Richtung R verlaufend und in radialer Richtung R eine Moderatorüberdeckung erzeugend aus dem Behältermantel 2 herausgefräst. Dabei weisen die Längskammern 3 in Längsrichtung auslaufende Enden 6 auf (vgl. Fig. 2).The container jacket 2 has on its outside Longitudinal chambers 3, which are filled with neutron moderator 4 and are closed by welded-on segment sheets 5. These longitudinal chambers 3 are, as you can easily see from the figures takes, at an obtuse angle to the radial direction R running and in the radial direction R a moderator coverage milled out of the container jacket 2 generating. The longitudinal chambers 3 end in the longitudinal direction Ends 6 (see Fig. 2).

Die Längskammern 3 sind durch sich über vier Längskammern 3 erstreckende Segmentbleche 5 verschlossen, die in Längsrichtung auf zwischen den Längskammern verlaufende Stege 7 (vgl. Fig. 1) und in Umfangsrichtung unterhalb der unteren sowie oberhalb der oberen auslaufenden Enden 6 aufgeschweißt sind. (vgl. Fig. 2). Im übrigen erkennt man aus den Figuren ohne weiteres, daß die Segmentbleche 5 auf ihrer Außenseite aufgeschweißte Längskühlrippen 8 aufweisen.The longitudinal chambers 3 are inherently four longitudinal chambers 3 extending segment sheets 5 closed in the longitudinal direction to webs 7 running between the longitudinal chambers (see Fig. 1) and in the circumferential direction below the lower and welded above the upper ends 6 are. (see Fig. 2). Otherwise you can see the figures without further ado that the segment sheets 5 longitudinal cooling fins welded onto the outside 8 exhibit.

Claims (6)

Abschirmbehälter aus Metall, insbesondere Stahl, für den Transport und die Lagerung von abgebrannten Kernreaktorbrennelementen und dergleichen, mit einem Behältermantel (2), der an seiner Außenseite mit Neutronenmoderator (4) gefüllte, durch aufgeschweißte Segmentbleche (5) verschlossene Längskammern (3) aufweist, dadurch gekennzeichnet, daß die Längskammern (3) in einem stumpfen Winkel zur radialen Richtung (R) verlaufend und in radialer Richtung (R) einer Moderatorüberdeckung erzeugend aus dem Behältermantel (2) herausgearbeitet sind.Shielding containers made of metal, in particular steel, for the transport and storage of spent nuclear reactor fuel elements and the like, with a container jacket (2) which has on the outside longitudinal chambers (3) filled with neutron moderator (4) and sealed by welded-on segment plates (5), characterized in that the longitudinal chambers (3) are machined from the container jacket (2) in an obtuse angle to the radial direction (R) and in the radial direction (R) producing a moderator cover. Abschirmbehälter nach Anspruch 1, dadurch gekennzeichnet, daß die Längskammern (3) aus dem Behältermantel (2) herausgefräst sind.Shielding container according to claim 1, characterized in that that the longitudinal chambers (3) from the container jacket (2) are milled out. Abschirmbehälter nach Anspruch 1 oder 2, dadurch gekennzeichnet, daß die Längskammern (3) in Längsrichtung auslaufende Enden (6) aufweisen.Shielding container according to claim 1 or 2, characterized in that the longitudinal chambers (3) end in the longitudinal direction Have ends (6). Abschirmbehälter nach einem der Ansprüche 1 bis 3, dadurch gekennzeichnet, daß die Längskammern (3) durch sich über mehrere, vorzugsweise vier Längskammern (3) erstreckende Segmentbleche (5) verschlossen sind.Shielding container according to one of claims 1 to 3, characterized characterized in that the longitudinal chambers (3) by themselves extending over several, preferably four, longitudinal chambers (3) Segment plates (5) are closed. Abschirmbehälter nach Anspruch 4, dadurch gekennzeichnet, daß die Segmentbleche (5) in Längsrichtung auf zwischen den Längskammern (3) verlaufende Stege (7) und in Umfangsrichtung unterhalb der unteren sowie oberhalb der oberen auslaufenden Enden (6) aufgeschweißt sind. Shielding container according to claim 4, characterized in that that the segment sheets (5) in the longitudinal direction webs (7) extending between the longitudinal chambers (3) and in Circumferential direction below the lower and above the the upper ends (6) are welded on. Abschirmbehälter nach einem der Ansprüche 1 bis 5, dadurch gekennzeichnet, daß die Segmentbleche (5) auf ihrer Außenseite aufgeschweißte Längskühlrippen (8) aufweisen.Shielding container according to one of claims 1 to 5, characterized characterized in that the segment sheets (5) on their Have welded longitudinal cooling fins (8) on the outside.
EP99120210A 1998-12-09 1999-10-09 Shielded container Expired - Lifetime EP1008994B1 (en)

Applications Claiming Priority (2)

Application Number Priority Date Filing Date Title
DE19856685A DE19856685A1 (en) 1998-12-09 1998-12-09 Shielding container
DE19856685 1998-12-09

Publications (2)

Publication Number Publication Date
EP1008994A1 true EP1008994A1 (en) 2000-06-14
EP1008994B1 EP1008994B1 (en) 2003-09-10

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EP99120210A Expired - Lifetime EP1008994B1 (en) 1998-12-09 1999-10-09 Shielded container

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EP (1) EP1008994B1 (en)
CZ (1) CZ289913B6 (en)
DE (2) DE19856685A1 (en)

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RU2453006C1 (en) * 2011-02-02 2012-06-10 Федеральное государственное унитарное предприятие "Российский Федеральный ядерный центр - Всероссийский научно-исследовательский институт экспериментальной физики" - ФГУП "РФЯЦ-ВНИИЭФ" Container to transport spent nuclear fuel
RU2463677C1 (en) * 2011-04-22 2012-10-10 Открытое акционерное общество "Конструкторское бюро специального машиностроения" Shipping packaging set for spent fuel assemblies of nuclear reactors
RU2459295C1 (en) * 2011-04-22 2012-08-20 Открытое акционерное общество "Конструкторское бюро специального машиностроения" Outer container set for used nuclear reactor fuel rod arrays
RU2458417C1 (en) * 2011-04-22 2012-08-10 Открытое акционерное общество "Конструкторское бюро специального машиностроения" Cover for spent fuel assemblies
RU2465662C1 (en) * 2011-07-20 2012-10-27 Открытое акционерное общество "Конструкторское бюро специального машиностроения" Container for transportation and/or storage of spent nuclear fuel
RU2486614C1 (en) * 2011-11-02 2013-06-27 Федеральное государственное бюджетное образовательное учреждение высшего профессионального образования "Петрозаводский государственный университет" Method to manufacture device for storage and transportation of spent nuclear fuel
RU2479876C1 (en) * 2011-11-10 2013-04-20 Открытое акционерное общество "Конструкторское бюро специального машиностроения" Container to transport and/or store spent nuclear fuel
RU2593273C1 (en) * 2015-08-04 2016-08-10 Федеральное государственное унитарное предприятие "Российский Федеральный ядерный центр - Всероссийский научно-исследовательский институт экспериментальной физики" (ФГУП "РФЯЦ-ВНИИЭФ") Container for spent nuclear fuel transportation and storage
RU2593388C1 (en) * 2015-08-04 2016-08-10 Федеральное государственное унитарное предприятие "Российский Федеральный ядерный центр - Всероссийский научно-исследовательский институт экспериментальной физики" (ФГУП "РФЯЦ-ВНИИЭФ") Cover for placing and storing of spent fuel assemblies of vver-1000 reactor
RU171909U1 (en) * 2016-12-07 2017-06-21 Федеральное государственное бюджетное образовательное учреждение высшего образования "Петрозаводский государственный университет" TUK CONTAINER WITH REMOVABLE COVER
RU2642449C1 (en) * 2017-01-10 2018-01-25 Федеральное государственное бюджетное образовательное учреждение высшего образования "Петрозаводский государственный университет" Container for tp with casing from high-strength spheroidal graphite cast iron
RU2646852C1 (en) * 2017-01-10 2018-03-12 Федеральное государственное бюджетное образовательное учреждение высшего образования "Петрозаводский государственный университет" Method of manufacture of container casing for tuk with casing from high-duty cast iron with globular graphite
RU2707871C1 (en) * 2019-03-27 2019-12-02 Акционерное общество "Логистический центр ЯТЦ" (АО "ЛЦ ЯТЦ") Container cover for transportation and storage of spent reactor fuel assembly

Citations (7)

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Publication number Priority date Publication date Assignee Title
FR1237612A (en) * 1958-10-17 1960-07-29 Edlow Lead Company Receptacle for the transport of radioactive materials
FR2074726A7 (en) * 1970-01-22 1971-10-08 Robatel Slpi Composite packaging material esp - for radio chemicals
DE2255996A1 (en) * 1971-11-15 1973-05-24 Lemer & Cie TRANSPORT VESSEL
FR2454157A1 (en) * 1979-04-14 1980-11-07 Transnuklear Gmbh SHIELDED CONTAINER FOR TRANSPORTING AND / OR STORING BURNED NUCLEAR FUEL ELEMENTS
EP0087350A1 (en) * 1982-02-12 1983-08-31 Framatome Neutron shielding device for radio-active material
DE3620737C1 (en) * 1986-06-20 1987-10-01 Wiederaufarbeitung Von Kernbre Double container system for the transport and storage of radioactive substances
DE4402282C1 (en) * 1994-01-27 1995-04-13 Apparate Und Anlagenbau Gmbh Method of making a welded connection, and transport and storage container produced according to this method for spent nuclear fuel assemblies

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DE2740933C2 (en) * 1977-09-10 1982-11-25 GNS Gesellschaft für Nuklear-Service mbH, 4300 Essen Transport and storage containers for radioactive substances, especially irradiated nuclear reactor fuel elements

Patent Citations (7)

* Cited by examiner, † Cited by third party
Publication number Priority date Publication date Assignee Title
FR1237612A (en) * 1958-10-17 1960-07-29 Edlow Lead Company Receptacle for the transport of radioactive materials
FR2074726A7 (en) * 1970-01-22 1971-10-08 Robatel Slpi Composite packaging material esp - for radio chemicals
DE2255996A1 (en) * 1971-11-15 1973-05-24 Lemer & Cie TRANSPORT VESSEL
FR2454157A1 (en) * 1979-04-14 1980-11-07 Transnuklear Gmbh SHIELDED CONTAINER FOR TRANSPORTING AND / OR STORING BURNED NUCLEAR FUEL ELEMENTS
EP0087350A1 (en) * 1982-02-12 1983-08-31 Framatome Neutron shielding device for radio-active material
DE3620737C1 (en) * 1986-06-20 1987-10-01 Wiederaufarbeitung Von Kernbre Double container system for the transport and storage of radioactive substances
DE4402282C1 (en) * 1994-01-27 1995-04-13 Apparate Und Anlagenbau Gmbh Method of making a welded connection, and transport and storage container produced according to this method for spent nuclear fuel assemblies

Also Published As

Publication number Publication date
DE19856685A1 (en) 2000-06-15
DE59906938D1 (en) 2003-10-16
CZ437899A3 (en) 2000-06-14
CZ289913B6 (en) 2002-04-17
EP1008994B1 (en) 2003-09-10

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