EP1434239B1 - Container for transporting and storing heat releasing materials, spent nuclear fuel assemblies or vitrified high active waste comprising shells - Google Patents

Container for transporting and storing heat releasing materials, spent nuclear fuel assemblies or vitrified high active waste comprising shells Download PDF

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Publication number
EP1434239B1
EP1434239B1 EP02028964A EP02028964A EP1434239B1 EP 1434239 B1 EP1434239 B1 EP 1434239B1 EP 02028964 A EP02028964 A EP 02028964A EP 02028964 A EP02028964 A EP 02028964A EP 1434239 B1 EP1434239 B1 EP 1434239B1
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EP
European Patent Office
Prior art keywords
container
transport
shafts
storage container
container body
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 - Lifetime
Application number
EP02028964A
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German (de)
French (fr)
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EP1434239A1 (en
Inventor
Konrad Gluschke
Roland Hüggenberg
Helmut KÜHL
Roger Vallentin
Berthold Klöhn
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.)
GNS Gesellschaft fuer Nuklearservice mbH
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GNS Gesellschaft fuer Nuklearservice mbH
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Publication date
Application filed by GNS Gesellschaft fuer Nuklearservice mbH filed Critical GNS Gesellschaft fuer Nuklearservice mbH
Priority to AT02028964T priority Critical patent/ATE385607T1/en
Priority to DE50211653T priority patent/DE50211653D1/en
Priority to EP02028964A priority patent/EP1434239B1/en
Priority to JP2003411999A priority patent/JP4815100B2/en
Publication of EP1434239A1 publication Critical patent/EP1434239A1/en
Application granted granted Critical
Publication of EP1434239B1 publication Critical patent/EP1434239B1/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

Definitions

  • the invention relates to a transport and storage container for heat-generating radioactive substances, in particular spent nuclear reactor fuel elements or HAW (high active waste) -Gaskaskillen
  • Transport and storage containers for radioactive materials or substances are well known in practice.
  • DE 197 34 166 A relates to a transport container with compartments for spent nuclear reactor fuel elements, which have already been enclosed gas-tight in capsules in the nuclear reactor.
  • Plate-shaped components made of absorber materials and moderator materials are attached to the inside of the radiation protection envelope of the transport container and shield fast neutrons.
  • Out EP 0 036 982 a basket for transport and / or storage containers for radioactive materials is known, which consists of graphite. Shafts for receiving the radioactive material are arranged in the graphitic insert basket.
  • EP 0 036 954 discloses a container for transporting and / or storing radioactive material, the neutron shield is disposed between the outer body of the container and the inner lining of the body.
  • the empty shafts remain regularly unused because they are too small.
  • For the shielding of the neutron radiation is a thermalization of the fast neutrons by hydrogen-containing materials in the container body or by external neutron moderators or - as a second possibility - by hydrogenated, borated materials, eg. As in the form of plastics, with additional Sekundärgammaabstrahlung, which are arranged on the outside of the container wall, accomplished.
  • the secondary gamma radiation leads to an increase in the total gamma dose rate at the outside of the container, in particular at weak points. Weaknesses of the neutron shield are regularly by means of additional shielding outside the container, eg. B. on his caddy, collected. Everything is very complicated and needs improvement.
  • the invention has the object of providing a transport and storage container of the type mentioned in such a way that the required reduction in the total level of neutron dose rate is achieved in a simpler manner than before.
  • the invention teaches a transport and storage container for heat-generating radioactive materials, in particular spent nuclear reactor fuel elements or HAW (high active waste) glass kokillen, consisting of a Neutronenmoderatormaterial having metallic container body with associated closure elements and arranged in the container body basket, which receiving shafts has empty wells for the radioactive substances and between the receiving wells, wherein at least the peripheral empty shafts are filled with graphite-containing neutron moderator material and wherein the neutron moderator material located in the empty shafts is at least partially provided with metal sheaths and wherein the metal sheaths are bolted to the container or are braced over the screwed to the container wall guide rails with the container body.
  • HAW high active waste glass kokillen
  • the invention is based on the recognition that graphite is not only an excellent neutron moderator material, but the high thermal conductivity and the radiation coefficient of the graphite also have extremely favorable effects on the heat dissipation. Consequently, the measures described also significantly reduce the temperature of the radioactive substances.
  • the peripheral empty shafts are designed like a whip.
  • the Neutronenmoderatormaterial exists preferably made of pressed graphite. It is advantageously formed columnar.
  • the neutron moderator material located in the voids is at least partially provided with metal sheaths according to the invention. These are inventively bolted to improve the heat conduction with the container body or clamped on screwed to the container body wall guide rails with the container body. For the same reason, it is also advisable to manufacture the metal shells made of copper or steel. Incidentally, it is also advisable to occupy head and / or foot-side container cavities with graphite.
  • the transport and storage container shown in the figure is intended for heat-generating radioactive substances, in particular spent nuclear reactor fuel elements or HAW (high active waste) glass molds and consists in its basic structure of a Neutronenmoderatormaterial 1 having metallic container body 2 with associated closure elements, not in detail are shown.
  • a support basket 3 is arranged, the receiving shafts 4 for the radioactive substances and between the receiving shafts empty shafts 5 has.
  • the peripheral empty shafts 5 are filled with graphite-containing neutron moderator material 1.
  • the peripheral empty wells 5 and, correspondingly, the neutron moderator material 1 located therein are designed like a whip.
  • this neutron moderator material 1 consists of pressed graphite columns. These graphite columns are provided over part of their circumference with metal sheaths 6 made of copper or steel, which are bolted to the container body 1. But you could also be clamped on bolted to the container body wall guide rails with the container head.
  • head and / or foot-side container cavities are also covered with graphite.

Abstract

A transport and storage container for a heat generating radioactive material comprises a metallic container (2) that includes a neutron moderating material (1), closure elements, and a carrier (3) in the container, which has compartments (4) for the radioactive material. Empty compartments are located between the compartments that hold the waste. The peripheral empty compartments (5) are filled with a graphite moderating material.

Description

Die Erfindung betrifft einen Transport- und Lagerbehälter für wärmeentwickelnde radioaktive Stoffe, insbesondere abgebrannte Kernreaktorbrennelemente oder HAW (high active waste)-GlaskokillenThe invention relates to a transport and storage container for heat-generating radioactive substances, in particular spent nuclear reactor fuel elements or HAW (high active waste) -Gaskaskillen

Transport- und Lagerbehälter für radioaktive Materialien bzw. Stoffe sind aus der Praxis allgemein bekannt. DE 197 34 166 A betrifft einen Transportbehälter mit Fächern für abgebrannte Kernreaktorbrennelemente, die bereits im Kernreaktor gasdicht in Kapseln eingeschlossen wurden. Plattenförmige Bauteile aus Absorbermaterialien und Moderatorenmaterialien werden an der Innenseite der Strahlenschutzhülle des Transportbehälters befestigt und schirmen schnelle Neutronen ab. Aus EP 0 036 982 ist ein Einsatzkorb für Transport- und/oder Lagerbehälter für radioaktive Materialien bekannt, der aus Graphit besteht. In dem graphitischen Einsatzkorb sind Schächte zur Aufnahme des radioaktiven Materials angeordnet. EP 0 036 954 offenbart einen Behälter zum Transport und/oder Lagerung radioaktiver Stoffe, dessen Neutronenabschirmung zwischen dem äußeren Grundkörper des Behälters und der inneren Auskleidung des Grundkörpers angeordnet ist. Bei aus der Praxis bekannten Transport- und Lagerbehältern der genannten Art bleiben die Leerschächte regelmäßig ungenutzt, da sie zu klein sind. Für die Abschirmung der Neutronenstrahlung wird eine Thermalisierung der schnellen Neutronen durch wasserstoffhaltige Materialien im Behälterkörper oder durch außen liegende Neutronenmoderatoren oder - als zweite Möglichkeit - durch wasserstoffhaltige, borierte Materialien, z. B. in Form von Kunststoffen, mit zusätzlicher Sekundärgammaabstrahlung, die außen an der Behälterwand angeordnet sind, bewerkstelligt. Die sekundäre Gammastrahlung führt zur Erhöhung der Gesamtgammadosisleistung an der Behälteraußenseite insbesondere an Schwachpunkten. Schwachstellen der Neutronenabschirmung werden regelmäßig mittels zusätzlicher Abschirmmaterialien außerhalb des Behälters, z. B. an seinem Transportgestell, aufgefangen. Alles das ist sehr aufwendig und verbesserungswürdig.Transport and storage containers for radioactive materials or substances are well known in practice. DE 197 34 166 A relates to a transport container with compartments for spent nuclear reactor fuel elements, which have already been enclosed gas-tight in capsules in the nuclear reactor. Plate-shaped components made of absorber materials and moderator materials are attached to the inside of the radiation protection envelope of the transport container and shield fast neutrons. Out EP 0 036 982 a basket for transport and / or storage containers for radioactive materials is known, which consists of graphite. Shafts for receiving the radioactive material are arranged in the graphitic insert basket. EP 0 036 954 discloses a container for transporting and / or storing radioactive material, the neutron shield is disposed between the outer body of the container and the inner lining of the body. In known from practice transport and storage containers of the type mentioned, the empty shafts remain regularly unused because they are too small. For the shielding of the neutron radiation is a thermalization of the fast neutrons by hydrogen-containing materials in the container body or by external neutron moderators or - as a second possibility - by hydrogenated, borated materials, eg. As in the form of plastics, with additional Sekundärgammaabstrahlung, which are arranged on the outside of the container wall, accomplished. The secondary gamma radiation leads to an increase in the total gamma dose rate at the outside of the container, in particular at weak points. Weaknesses of the neutron shield are regularly by means of additional shielding outside the container, eg. B. on his caddy, collected. Everything is very complicated and needs improvement.

Der Erfindung liegt die Aufgabe zugrunde, einen Transport- und Lagerbehälter der eingangs genannten Art so auszubilden, dass die erforderliche Senkung des Gesamtpegels der Neutronendosisleistung auf einfachere Art und Weise als bisher erreicht wird.The invention has the object of providing a transport and storage container of the type mentioned in such a way that the required reduction in the total level of neutron dose rate is achieved in a simpler manner than before.

Zur Lösung des technischen Problems lehrt die Erfindung einen Transport- und Lagerbehälter für wärmeentwickelnde radioaktive Stoffe, insbesondere abgebrannte Kernreaktorbrennelemente oder HAW (high active waste)-Glaskokillen, bestehend aus einem Neutronenmoderatormaterial aufweisenden metallischen Behälterkörper mit zugeordneten Verschlusselementen und einem im Behälterkörper angeordneten Tragkorb, welcher Aufnahmeschächte für die radioaktiven Stoffe und zwischen den Aufnahmeschächten Leerschächte aufweist,
wobei zumindest die peripheren Leerschächte mit graphithaltigem Neutronenmoderatormaterial verfüllt sind und wobei das in den Leerschächten befindliche Neutronenmoderatormaterial zumindest teilweise mit Metallhüllen versehen ist
und wobei die Metallhüllen mit dem Behälter verschraubt sind oder über an der Behälterwand verschraubte Führungsleisten mit dem Behälterkörper verspannt sind.To solve the technical problem, the invention teaches a transport and storage container for heat-generating radioactive materials, in particular spent nuclear reactor fuel elements or HAW (high active waste) glass kokillen, consisting of a Neutronenmoderatormaterial having metallic container body with associated closure elements and arranged in the container body basket, which receiving shafts has empty wells for the radioactive substances and between the receiving wells,
wherein at least the peripheral empty shafts are filled with graphite-containing neutron moderator material and wherein the neutron moderator material located in the empty shafts is at least partially provided with metal sheaths
and wherein the metal sheaths are bolted to the container or are braced over the screwed to the container wall guide rails with the container body.

Die Erfindung geht hierbei von der Erkenntnis aus, dass Graphit nicht nur ein hervorragendes Neutronenmoderatormaterial ist, sondern die hohe Wärmeleitfähigkeit und der Strahlungskoeffizient des Graphites sich auch äußerst günstig auf die Wärmeabfuhr auswirken. Folglich ist durch die beschriebenen Maßnahmen auch eine deutliche Senkung der Temperatur der radioaktiven Stoffe gegeben.The invention is based on the recognition that graphite is not only an excellent neutron moderator material, but the high thermal conductivity and the radiation coefficient of the graphite also have extremely favorable effects on the heat dissipation. Consequently, the measures described also significantly reduce the temperature of the radioactive substances.

Für die weitere Ausgestaltung bestehen im Rahmen der Erfindung mehrere Möglichkeiten. So sind nach einer bevorzugten Ausführungsform die peripheren Leerschächte zwickelförmig gestaltet. Das Neutronenmoderatormaterial besteht vorzugsweise aus gepresstem Graphit. Es ist vorteilhafterweise säulenförmig ausgebildet. Das in den Leerräumen befindliche Neutronenmoderatormaterial ist erfindungsgemäß zumindest teilweise mit Metallhüllen versehen. Diese sind zur Verbesserung der Wärmeleitung erfindungsgemäß mit dem Behälterkörper verschraubt oder über an der Behälterkörperwand verschraubte Führungsleisten mit dem Behälterkörper verspannt. Aus dem gleichen Grunde empfiehlt es sich auch, die Metallhüllen aus Kupfer oder Stahl zu fertigen. Im Übrigen empfiehlt es sich außerdem, kopf- und/oder fußseitige Behälterhohlräume mit Graphit zu belegen.For the further embodiment, there are several possibilities within the scope of the invention. Thus, according to a preferred embodiment, the peripheral empty shafts are designed like a whip. The Neutronenmoderatormaterial exists preferably made of pressed graphite. It is advantageously formed columnar. The neutron moderator material located in the voids is at least partially provided with metal sheaths according to the invention. These are inventively bolted to improve the heat conduction with the container body or clamped on screwed to the container body wall guide rails with the container body. For the same reason, it is also advisable to manufacture the metal shells made of copper or steel. Incidentally, it is also advisable to occupy head and / or foot-side container cavities with graphite.

Im Folgenden wird die Erfindung anhand einer ein Ausführungsbeispiel darstellenden Zeichnung näher erläutert. Die einzige Figur zeigt im Querschnitt einen Transport- und Lagerbehälter.In the following the invention will be explained in more detail with reference to a drawing illustrating an embodiment. The single figure shows in cross section a transport and storage container.

Der in der Figur dargestellte Transport- und Lagerbehälter ist für wärmeentwickelnde radioaktive Stoffe, insbesondere abgebrannte Kernreaktorbrennelemente oder HAW (high active waste)-Glaskokillen bestimmt und besteht in seinem grundsätzlichen Aufbau aus einem Neutronenmoderatormaterial 1 aufweisenden metallischen Behälterkörper 2 mit zugeordneten Verschlusselementen, die im Einzelnen nicht dargestellt sind. Im Behälterkörper 2 ist ein Tragkorb 3 angeordnet, der Aufnahmeschächte 4 für die radioaktiven Stoffe und zwischen den Aufnahmeschächten Leerschächte 5 aufweist.The transport and storage container shown in the figure is intended for heat-generating radioactive substances, in particular spent nuclear reactor fuel elements or HAW (high active waste) glass molds and consists in its basic structure of a Neutronenmoderatormaterial 1 having metallic container body 2 with associated closure elements, not in detail are shown. In the container body 2, a support basket 3 is arranged, the receiving shafts 4 for the radioactive substances and between the receiving shafts empty shafts 5 has.

Wie aus der Figur ersichtlich ist, sind die peripheren Leerschächte 5 mit graphithaltigem Neutronenmoderatormaterial 1 verfüllt. Die peripheren Leerschächte 5 und entsprechend auch das darin befindliche Neutronenmoderatormaterial 1 sind zwickelförmig gestaltet. Im Ausführungsbeispiel besteht dieses Neutronenmoderatormaterial 1 aus gepressten Graphitsäulen. Diese Graphitsäulen sind über einen Teil ihres Umfanges mit Metallhüllen 6 aus Kupfer oder Stahl versehen, die mit dem Behälterkörper 1 verschraubt sind. Sie könnten aber auch über an der Behälterkörperwand verschraubte Führungsleisten mit dem Behälterkopf verspannt sein.As can be seen from the figure, the peripheral empty shafts 5 are filled with graphite-containing neutron moderator material 1. The peripheral empty wells 5 and, correspondingly, the neutron moderator material 1 located therein are designed like a whip. In the exemplary embodiment, this neutron moderator material 1 consists of pressed graphite columns. These graphite columns are provided over part of their circumference with metal sheaths 6 made of copper or steel, which are bolted to the container body 1. But you could also be clamped on bolted to the container body wall guide rails with the container head.

Im Einzelnen nicht dargestellt ist, dass kopf- und/oder fußseitige Behälterhohlräume ebenfalls mit Graphit belegt sind.It is not shown in detail that head and / or foot-side container cavities are also covered with graphite.

Claims (6)

  1. Transport and storage container for heat-generating radioactive substances, in particular spent nuclear reactor fuel elements or HAW (high active waste) glass units, said container consisting of a metal container body (2) containing a neutron moderator material (1) and having associated closure elements, and a carrying basket (3) which is arranged in the container body (2) and comprises holding shafts (4) for the radioactive substances and empty shafts (5) between the holding shafts (4),
    wherein at least the peripheral empty shafts (5) are filled with graphite-containing neutron moderator material (1) and wherein the neutron moderator material (1) located in the empty shafts (5) is at least partially provided with metal casings (6),
    characterised in that the metal casings (6) are screwed onto the container body (2) or are secured to the container body (2) via guide strips screwed onto the container body wall.
  2. Transport and storage container according to claim 1, wherein the peripheral empty shafts (5) are wedge-shaped.
  3. Transport and storage container according to claim 1 or 2, wherein the neutron moderator material (1) consists of pressed graphite.
  4. Transport and storage container according to one of claims 1 to 3, wherein the neutron moderator material (1) located in the empty shafts (5) is column-shaped.
  5. Transport and storage container according to one of claims 1 to 4, wherein the metal casings (6) are made of copper or steel.
  6. Transport and storage container according to one of claims 1 to 5, wherein hollow spaces at the top and/or bottom of the container are filled with graphite.
EP02028964A 2002-12-24 2002-12-24 Container for transporting and storing heat releasing materials, spent nuclear fuel assemblies or vitrified high active waste comprising shells Expired - Lifetime EP1434239B1 (en)

Priority Applications (4)

Application Number Priority Date Filing Date Title
AT02028964T ATE385607T1 (en) 2002-12-24 2002-12-24 TRANSPORT AND STORAGE CONTAINERS FOR HEAT GENERATING RADIOACTIVE SUBSTANCES, IN PARTICULAR Spent NUCLEAR REACTOR FUELS OR HAW GLASS MOLDS
DE50211653T DE50211653D1 (en) 2002-12-24 2002-12-24 Transport and storage containers for heat-generating radioactive substances, in particular spent nuclear reactor fuel elements or HAW glass canisters
EP02028964A EP1434239B1 (en) 2002-12-24 2002-12-24 Container for transporting and storing heat releasing materials, spent nuclear fuel assemblies or vitrified high active waste comprising shells
JP2003411999A JP4815100B2 (en) 2002-12-24 2003-12-10 Transport and storage containers for radioactive materials that generate heat, especially spent nuclear fuel elements or high-level radioactive waste-glass solids

Applications Claiming Priority (1)

Application Number Priority Date Filing Date Title
EP02028964A EP1434239B1 (en) 2002-12-24 2002-12-24 Container for transporting and storing heat releasing materials, spent nuclear fuel assemblies or vitrified high active waste comprising shells

Publications (2)

Publication Number Publication Date
EP1434239A1 EP1434239A1 (en) 2004-06-30
EP1434239B1 true EP1434239B1 (en) 2008-02-06

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EP02028964A Expired - Lifetime EP1434239B1 (en) 2002-12-24 2002-12-24 Container for transporting and storing heat releasing materials, spent nuclear fuel assemblies or vitrified high active waste comprising shells

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EP (1) EP1434239B1 (en)
JP (1) JP4815100B2 (en)
AT (1) ATE385607T1 (en)
DE (1) DE50211653D1 (en)

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RU2686476C1 (en) * 2018-06-05 2019-04-29 Александр Натанович Капилевич Container cover for spent nuclear fuel transportation and storage

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DE102004049236B4 (en) * 2004-10-09 2006-07-13 GNS Gesellschaft für Nuklear-Service mbH Transport and/or storage container for nuclear fuel elements, comprises a carrier inside the container, and a number of receiving sections for the fuel elements
DE102010003289B4 (en) * 2010-03-25 2017-08-24 Ald Vacuum Technologies Gmbh Containers for the storage of radioactive waste and process for its production
JP6143573B2 (en) * 2013-06-20 2017-06-07 三菱重工業株式会社 Radioactive substance storage basket and radioactive substance storage container
US10878972B2 (en) 2019-02-21 2020-12-29 Deep Isolation, Inc. Hazardous material repository systems and methods

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DE3012310A1 (en) * 1980-03-29 1981-10-08 Transnuklear Gmbh, 6450 Hanau INSERT BASKET FOR RADIOACTIVE MATERIAL IN TRANSPORT AND / OR STORAGE CONTAINERS
DE3017985A1 (en) * 1980-05-10 1981-11-12 Vox lumatic GmbH, 7302 Ostfildern Transport and storage vessel for radioactive materials - has shielding conductive material esp. graphite between thick outer wall and inner sealed containment
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JP3150669B2 (en) * 1999-09-02 2001-03-26 三菱重工業株式会社 Cask

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* Cited by examiner, † Cited by third party
Publication number Priority date Publication date Assignee Title
RU2686476C1 (en) * 2018-06-05 2019-04-29 Александр Натанович Капилевич Container cover for spent nuclear fuel transportation and storage

Also Published As

Publication number Publication date
JP2004205503A (en) 2004-07-22
JP4815100B2 (en) 2011-11-16
DE50211653D1 (en) 2008-03-20
EP1434239A1 (en) 2004-06-30
ATE385607T1 (en) 2008-02-15

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