EP1008994B1 - Shielded container - Google Patents
Shielded container Download PDFInfo
- Publication number
- EP1008994B1 EP1008994B1 EP99120210A EP99120210A EP1008994B1 EP 1008994 B1 EP1008994 B1 EP 1008994B1 EP 99120210 A EP99120210 A EP 99120210A EP 99120210 A EP99120210 A EP 99120210A EP 1008994 B1 EP1008994 B1 EP 1008994B1
- Authority
- EP
- European Patent Office
- Prior art keywords
- longitudinal
- longitudinal chambers
- fact
- chambers
- shielding container
- 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
Links
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
-
- 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, in particular steel, for the transport and storage of spent nuclear reactor fuel elements and the like according to the preamble of claim 1.
- the longitudinal chambers for the neutron moderator are formed by radial webs welded onto the container shell. This is complex and not satisfactory from a functional point of view. The entire heat generated in the shielding container must be dissipated to the surface by heat conduction via the chamber webs.
- Gamma radiation is to be shielded by the metal of the container shell and neutron radiation by the neutron moderator. If the radial webs are too thin, heat builds up and the internal temperatures in the shielding container are too high. If the radial webs are too thick, so-called neutron streaming occurs because of the lack of a neutron moderator. H. an increased dose rate due to neutrons on the surface. The thickness of the radial webs therefore always involves a compromise.
- the invention has for its object to provide a shielding container of the type mentioned so that it is easy to manufacture and reliable.
- the oblique arrangement of the longitudinal chambers enables optimum setting of the shielding properties for physical reasons.
- the gamma shield is close to the source and the neutron shield on the outer edge of the gamma shield. Due to the inclined position of the built-in neutron moderator, neutron streaming is excluded because the moderator webs overlap in the radial direction. The heat conduction is sufficiently achieved by the webs of the container base material.
- the longitudinal chambers are preferably milled out of the container jacket. It is advisable to design the longitudinal chambers with their ends tapering in the longitudinal direction.
- the longitudinal chambers should be closed by segment sheets extending over several, preferably four, longitudinal chambers. In this context, it is advisable to weld the segment sheets in the longitudinal direction onto webs running between the longitudinal chambers and in the circumferential direction below the lower and above the upper tapered ends.
- the segment sheets should be provided with welded-on longitudinal cooling fins on their outside before welding, so that later attachment to the shielding container is avoided.
- the shielding container shown in the figures consists of metal, in particular steel, and is intended for the transport and storage of spent nuclear reactor fuel elements or similar radioactive objects.
- it consists of a container jacket 2 provided with a bottom 1, onto which a cover (not shown) 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 plates 5. These longitudinal chambers 3, as can easily be seen from the figures, run at an obtuse angle to the radial direction R and are milled out of the container jacket 2 in the radial direction R to produce a moderator cover.
- the longitudinal chambers 3 have ends 6 that run in the longitudinal direction (cf. FIG. 2).
- the longitudinal chambers 3 are closed by segment sheets 5 which extend over four longitudinal chambers 3 and which extend in the longitudinal direction on webs 7 running between the longitudinal chambers (cf. FIG. 1) and in the circumferential direction below the lower one and welded above the upper ends 6. (see Fig. 2). Moreover, it can be seen from the figures without further ado that the segment sheets 5 have longitudinal cooling fins 8 welded onto their outside.
Description
Die Erfindung betrifft einen Abschirmbehälter aus Metall, insbesondere Stahl, für den Transport und die Lagerung von abgebrannten Kernreaktorbrennelementen und dergleichen gemäß dem Oberbegriff des Anspruchs 1.The invention relates to a shielding container made of metal, in particular steel, for the transport and storage of spent nuclear reactor fuel elements and the like according to the preamble of claim 1.
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 of this type known from practice, the longitudinal chambers for the neutron moderator are formed by radial webs welded onto the container shell. This is complex and not satisfactory from a functional point of view. The entire heat generated in the shielding container must be dissipated to the surface by heat conduction via the chamber webs. Gamma radiation is to be shielded by the metal of the container shell and neutron radiation by the neutron moderator. If the radial webs are too thin, heat builds up and the internal temperatures in the shielding container are too high. If the radial webs are too thick, so-called neutron streaming occurs because of the lack of a neutron moderator. H. an increased dose rate due to neutrons on the surface. The thickness of the radial webs therefore always involves 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 to provide a shielding container of the type mentioned so that it is easy to manufacture and reliable.
Die erfindungsgemäße Lösung dieser Aufgabe besteht darin, daß die Längskammern gemäß dem kennzeichnenden Teil des Anspruch 1 herausgearbeitet sind.The inventive solution to this problem is that the longitudinal chambers according to the characterizing part of Claim 1 are worked out.
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 enables optimum setting of the shielding properties for physical reasons. The gamma shield is close to the source and the neutron shield on the outer edge of the gamma shield. Due to the inclined position of the built-in neutron moderator, neutron streaming is excluded because the moderator webs overlap in the radial direction. The heat conduction is sufficiently achieved by the webs of the container base material.
Für die Ausgestaltung bestehen im Rahmen der Erfindung mehrere Möglichkeiten, deren bevorzugte nachfolgend aufgeführt sind:There are several possibilities for the configuration within the scope of the invention, the preferred of which are listed below:
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 milled out of the container jacket. It is advisable to design the longitudinal chambers with their ends tapering in the longitudinal direction. The longitudinal chambers should be closed by segment sheets extending over several, preferably four, longitudinal chambers. In this context, it is advisable to weld the segment sheets in the longitudinal direction onto webs running between the longitudinal chambers and in the circumferential direction below the lower and above the upper tapered ends. In addition, the segment sheets should be provided with welded-on longitudinal cooling fins on their outside before welding, so that later attachment to 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.
- 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 consists of metal, in particular steel, and is intended for the transport and storage of spent nuclear reactor fuel elements or similar radioactive objects. In its basic structure, it consists of a container jacket 2 provided with a bottom 1, onto which a cover (not shown) 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 plates 5. These longitudinal chambers 3, as can easily be seen from the figures, run at an obtuse angle to the radial direction R and are milled out of the container jacket 2 in the radial direction R to produce a moderator cover. The longitudinal chambers 3 have ends 6 that run in the longitudinal direction (cf. 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 closed by segment sheets 5 which extend over four longitudinal chambers 3 and which extend in the longitudinal direction on webs 7 running between the longitudinal chambers (cf. FIG. 1) and in the circumferential direction below the lower one and welded above the upper ends 6. (see Fig. 2). Moreover, it can be seen from the figures without further ado that the segment sheets 5 have longitudinal cooling fins 8 welded onto their outside.
Claims (5)
- A shielding container of metal, in particular, steel, for transporting and storing spent nuclear reactor fuel elements and the like, with an outer container wall (2), the outside of which contains longitudinal chambers (3) that are filled with a neutron moderator (4) and closed by welding on plates (5), wherein the longitudinal chambers (3) extend at an obtuse angle referred to the radial direction (R) and are arranged on the outer container wall (2) in the radial direction (R) such that a moderator cover is formed, characterized by the fact that the longitudinal chambers (3) are machined into the outer container wall (2) and closed with segmental plates (5) that extend over several longitudinal chambers (3).
- The shielding container according to Claim 1, characterized by the fact that the longitudinal chambers (3) have ends (6) that are tapered in the longitudinal direction.
- The shielding container according to Claim 1 or 2, characterized by the fact that the longitudinal chambers (3) are closed with segmental plates (5) that extend over four longitudinal chambers (3).
- The shielding container according to one of Claims 1 - 3, characterized by the fact that the segmental plates (5) are welded to webs (7) that extend between the longitudinal chambers (3) in the longitudinal direction, and by the fact that the segmental plates are welded to the outer container wall underneath the lower and above the upper tapered ends (6) in the circumferential direction.
- The shielding container according to one of Claims 1 - 4, characterized by the fact that the segmental plates (5) contain longitudinal cooling ribs (8) that are welded to their outer sides.
Applications Claiming Priority (2)
Application Number | Priority Date | Filing Date | Title |
---|---|---|---|
DE19856685 | 1998-12-09 | ||
DE19856685A DE19856685A1 (en) | 1998-12-09 | 1998-12-09 | Shielding container |
Publications (2)
Publication Number | Publication Date |
---|---|
EP1008994A1 EP1008994A1 (en) | 2000-06-14 |
EP1008994B1 true EP1008994B1 (en) | 2003-09-10 |
Family
ID=7890438
Family Applications (1)
Application Number | Title | Priority Date | Filing Date |
---|---|---|---|
EP99120210A Expired - Lifetime EP1008994B1 (en) | 1998-12-09 | 1999-10-09 | Shielded container |
Country Status (3)
Country | Link |
---|---|
EP (1) | EP1008994B1 (en) |
CZ (1) | CZ289913B6 (en) |
DE (2) | DE19856685A1 (en) |
Cited By (1)
Publication number | Priority date | Publication date | Assignee | Title |
---|---|---|---|---|
RU211868U1 (en) * | 2022-01-13 | 2022-06-24 | Акционерное общество "Инжиниринговая компания "АЭМ-технологии"(АО "АЭМ-технологии") | TRANSPORT PACKAGING FOR THE TRANSPORTATION OF SPENT NUCLEAR FUEL |
Families Citing this family (13)
Publication number | Priority date | Publication date | Assignee | Title |
---|---|---|---|---|
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 |
RU2458417C1 (en) * | 2011-04-22 | 2012-08-10 | Открытое акционерное общество "Конструкторское бюро специального машиностроения" | Cover for spent fuel assemblies |
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 |
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 |
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 |
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 |
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 |
Family Cites Families (8)
Publication number | Priority date | Publication date | Assignee | Title |
---|---|---|---|---|
LU37754A1 (en) * | 1958-10-17 | |||
FR2074726A7 (en) * | 1970-01-22 | 1971-10-08 | Robatel Slpi | Composite packaging material esp - for radio chemicals |
BE791334A (en) * | 1971-11-15 | 1973-03-01 | Lemer & Cie | PERFECTED DEVICE FOR AIR COOLING OF RADIOACTIVE PRODUCTS TRANSPORT CASTLES |
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 |
DE7911030U1 (en) * | 1979-04-14 | 1979-08-23 | Transnuklear Gmbh, 6450 Hanau | SHIELD CONTAINER FOR THE TRANSPORT AND / OR STORAGE OF BURNED FUEL ELEMENTS |
FR2521764A1 (en) * | 1982-02-12 | 1983-08-19 | Creusot Loire | NEUTRON PROTECTION DEVICE FOR RADIO-ACTIVE PRODUCT |
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 |
-
1998
- 1998-12-09 DE DE19856685A patent/DE19856685A1/en not_active Withdrawn
-
1999
- 1999-10-09 EP EP99120210A patent/EP1008994B1/en not_active Expired - Lifetime
- 1999-10-09 DE DE59906938T patent/DE59906938D1/en not_active Expired - Fee Related
- 1999-12-06 CZ CZ19994378A patent/CZ289913B6/en not_active IP Right Cessation
Cited By (1)
Publication number | Priority date | Publication date | Assignee | Title |
---|---|---|---|---|
RU211868U1 (en) * | 2022-01-13 | 2022-06-24 | Акционерное общество "Инжиниринговая компания "АЭМ-технологии"(АО "АЭМ-технологии") | TRANSPORT PACKAGING FOR THE TRANSPORTATION OF SPENT NUCLEAR FUEL |
Also Published As
Publication number | Publication date |
---|---|
DE59906938D1 (en) | 2003-10-16 |
CZ289913B6 (en) | 2002-04-17 |
DE19856685A1 (en) | 2000-06-15 |
CZ437899A3 (en) | 2000-06-14 |
EP1008994A1 (en) | 2000-06-14 |
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