EP1008994B1 - Conteneur blindé - Google Patents
Conteneur blindé 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.
Landscapes
- Physics & Mathematics (AREA)
- Engineering & Computer Science (AREA)
- General Engineering & Computer Science (AREA)
- High Energy & Nuclear Physics (AREA)
- Butt Welding And Welding Of Specific Article (AREA)
- Particle Accelerators (AREA)
Claims (5)
- Conteneur blindé en métal, en particulier en acier, pour le transport et le stockage d'éléments brûlés de combustion de réacteurs nucléaires et similaires, avec une chemise (2), qui présente sur sa face externe des cavités longitudinales (3) remplies de modérateur de neutrons (4) fermées par des tôles (5) soudées, les cavités longitudinales (3) s'étendant dans un angle obtus par rapport au sens radial (R) et un recouvrement formant un modérateur dans le sens radial (R) étant prévu sur la chemise du conteneur (2), caractérisé en ce que les cavités longitudinales (3) sont fraisées dans la chemise du conteneur (2) et fermées par des tôles segmentées (5) s'étendant sur plusieurs cavités longitudinales (3).
- Conteneur blindé selon la revendication 1, caractérisé en ce que les cavités longitudinales (3) présentent des extrémités (6) sortant dans le sens longitudinal.
- Conteneur blindé selon la revendication 1, caractérisé en ce que les cavités longitudinales (3) sont fermées par des tôles segmentées (5) s'étendant sur quatre cavités longitudinales (3).
- Conteneur blindé selon une des revendications 1 à 3, caractérisé en ce que les tôles segmentées (5) sont soudées dans le sens longitudinal sur des traverses (7) s'étendant entre les cavités longitudinales (3) et dans le sens du volume en dessous des extrémités sortantes (6) inférieures aussi qu'au dessus des supérieures.
- Conteneur blindé selon une des revendications 1 à 4, caractérisé en ce que les tôles segmentées (5) présentent des nervures de refroidissement longitudinales (8) soudées sur leur face externe.
Applications Claiming Priority (2)
Application Number | Priority Date | Filing Date | Title |
---|---|---|---|
DE19856685 | 1998-12-09 | ||
DE19856685A DE19856685A1 (de) | 1998-12-09 | 1998-12-09 | Abschirmbehälter |
Publications (2)
Publication Number | Publication Date |
---|---|
EP1008994A1 EP1008994A1 (fr) | 2000-06-14 |
EP1008994B1 true EP1008994B1 (fr) | 2003-09-10 |
Family
ID=7890438
Family Applications (1)
Application Number | Title | Priority Date | Filing Date |
---|---|---|---|
EP99120210A Expired - Lifetime EP1008994B1 (fr) | 1998-12-09 | 1999-10-09 | Conteneur blindé |
Country Status (3)
Country | Link |
---|---|
EP (1) | EP1008994B1 (fr) |
CZ (1) | CZ289913B6 (fr) |
DE (2) | DE19856685A1 (fr) |
Cited By (1)
Publication number | Priority date | Publication date | Assignee | Title |
---|---|---|---|---|
RU211868U1 (ru) * | 2022-01-13 | 2022-06-24 | Акционерное общество "Инжиниринговая компания "АЭМ-технологии"(АО "АЭМ-технологии") | Транспортный упаковочный комплект для перевозки отработавшего ядерного топлива |
Families Citing this family (13)
Publication number | Priority date | Publication date | Assignee | Title |
---|---|---|---|---|
RU2453006C1 (ru) * | 2011-02-02 | 2012-06-10 | Федеральное государственное унитарное предприятие "Российский Федеральный ядерный центр - Всероссийский научно-исследовательский институт экспериментальной физики" - ФГУП "РФЯЦ-ВНИИЭФ" | Контейнер для транспортирования отработавшего ядерного топлива |
RU2458417C1 (ru) * | 2011-04-22 | 2012-08-10 | Открытое акционерное общество "Конструкторское бюро специального машиностроения" | Чехол для отработавших тепловыделяющих сборок |
RU2459295C1 (ru) * | 2011-04-22 | 2012-08-20 | Открытое акционерное общество "Конструкторское бюро специального машиностроения" | Транспортный упаковочный комплект для отработавших тепловыделяющих сборок ядерных реакторов |
RU2463677C1 (ru) * | 2011-04-22 | 2012-10-10 | Открытое акционерное общество "Конструкторское бюро специального машиностроения" | Транспортный упаковочный комплект для отработавших тепловыделяющих сборок ядерных реакторов |
RU2465662C1 (ru) * | 2011-07-20 | 2012-10-27 | Открытое акционерное общество "Конструкторское бюро специального машиностроения" | Контейнер для транспортировки и/или хранения отработавшего ядерного топлива |
RU2486614C1 (ru) * | 2011-11-02 | 2013-06-27 | Федеральное государственное бюджетное образовательное учреждение высшего профессионального образования "Петрозаводский государственный университет" | Способ изготовления устройства для хранения и транспортировки отработавшего ядерного топлива |
RU2479876C1 (ru) * | 2011-11-10 | 2013-04-20 | Открытое акционерное общество "Конструкторское бюро специального машиностроения" | Контейнер для транспортировки и/или хранения отработавшего ядерного топлива |
RU2593273C1 (ru) * | 2015-08-04 | 2016-08-10 | Федеральное государственное унитарное предприятие "Российский Федеральный ядерный центр - Всероссийский научно-исследовательский институт экспериментальной физики" (ФГУП "РФЯЦ-ВНИИЭФ") | Контейнер для транспортирования и хранения отработавшего ядерного топлива |
RU2593388C1 (ru) * | 2015-08-04 | 2016-08-10 | Федеральное государственное унитарное предприятие "Российский Федеральный ядерный центр - Всероссийский научно-исследовательский институт экспериментальной физики" (ФГУП "РФЯЦ-ВНИИЭФ") | Чехол для размещения и хранения отработавших тепловыделяющих сборок реактора ввэр-1000 |
RU171909U1 (ru) * | 2016-12-07 | 2017-06-21 | Федеральное государственное бюджетное образовательное учреждение высшего образования "Петрозаводский государственный университет" | Контейнер для тук с несъемным чехлом |
RU2642449C1 (ru) * | 2017-01-10 | 2018-01-25 | Федеральное государственное бюджетное образовательное учреждение высшего образования "Петрозаводский государственный университет" | Контейнер для тук с чехлом из высокопрочного чугуна с шаровидным графитом |
RU2646852C1 (ru) * | 2017-01-10 | 2018-03-12 | Федеральное государственное бюджетное образовательное учреждение высшего образования "Петрозаводский государственный университет" | Способ изготовления корпуса контейнера для тук с чехлом из высокопрочного чугуна с шаровидным графитом |
RU2707871C1 (ru) * | 2019-03-27 | 2019-12-02 | Акционерное общество "Логистический центр ЯТЦ" (АО "ЛЦ ЯТЦ") | Чехол контейнера для транспортирования и хранения отработавших тепловыделяющих сборок |
Family Cites Families (8)
Publication number | Priority date | Publication date | Assignee | Title |
---|---|---|---|---|
BE583252A (fr) * | 1958-10-17 | |||
FR2074726A7 (en) * | 1970-01-22 | 1971-10-08 | Robatel Slpi | Composite packaging material esp - for radio chemicals |
BE791334A (fr) * | 1971-11-15 | 1973-03-01 | Lemer & Cie | Dispositif perfectionne pour le refroidissement par air de chateau de transport de produits radioactifs |
DE2740933C2 (de) * | 1977-09-10 | 1982-11-25 | GNS Gesellschaft für Nuklear-Service mbH, 4300 Essen | Transport- bzw. Lagerbehälter für radioaktive Stoffe, insbesondere bestrahlte Kernreaktorbrennelemente |
DE7911030U1 (de) * | 1979-04-14 | 1979-08-23 | Transnuklear Gmbh, 6450 Hanau | Abschirmbehaelter zum transport und/ oder zur lagerung abgebrannter brennelemente |
FR2521764A1 (fr) * | 1982-02-12 | 1983-08-19 | Creusot Loire | Dispositif de protection neutronique pour produit radio-actif |
DE3620737C1 (de) * | 1986-06-20 | 1987-10-01 | Wiederaufarbeitung Von Kernbre | Doppelbehaeltersystem zum Transport und zur Lagerung von radioaktiven Stoffen |
DE4402282C1 (de) * | 1994-01-27 | 1995-04-13 | Apparate Und Anlagenbau Gmbh | Verfahren zur Herstellung einer Schweißverbindung und nach diesem Verfahren hergestellter Transport- und Lagerbehälter für abgebrannte Kernbrennstoffkassetten |
-
1998
- 1998-12-09 DE DE19856685A patent/DE19856685A1/de not_active Withdrawn
-
1999
- 1999-10-09 EP EP99120210A patent/EP1008994B1/fr not_active Expired - Lifetime
- 1999-10-09 DE DE59906938T patent/DE59906938D1/de not_active Expired - Fee Related
- 1999-12-06 CZ CZ19994378A patent/CZ289913B6/cs not_active IP Right Cessation
Cited By (1)
Publication number | Priority date | Publication date | Assignee | Title |
---|---|---|---|---|
RU211868U1 (ru) * | 2022-01-13 | 2022-06-24 | Акционерное общество "Инжиниринговая компания "АЭМ-технологии"(АО "АЭМ-технологии") | Транспортный упаковочный комплект для перевозки отработавшего ядерного топлива |
Also Published As
Publication number | Publication date |
---|---|
DE19856685A1 (de) | 2000-06-15 |
CZ437899A3 (cs) | 2000-06-14 |
DE59906938D1 (de) | 2003-10-16 |
CZ289913B6 (cs) | 2002-04-17 |
EP1008994A1 (fr) | 2000-06-14 |
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