EP0143398A2 - Récipient en particulier pour substances radioactives - Google Patents
Récipient en particulier pour substances radioactives Download PDFInfo
- Publication number
- EP0143398A2 EP0143398A2 EP84113774A EP84113774A EP0143398A2 EP 0143398 A2 EP0143398 A2 EP 0143398A2 EP 84113774 A EP84113774 A EP 84113774A EP 84113774 A EP84113774 A EP 84113774A EP 0143398 A2 EP0143398 A2 EP 0143398A2
- Authority
- EP
- European Patent Office
- Prior art keywords
- container
- inner container
- heat dissipation
- tube
- outer 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.)
- Granted
Links
Images
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
Definitions
- the invention relates to a container, in particular for radioactive substances such as radioactive liquids, with an inner container for receiving these substances and an outer container in which the inner container and heat insulating material are located between the inner and outer containers.
- the heat insulating material of this container between the inner and outer container consists e.g. made of phenolic resin foam. It is intended to prevent heat from entering the inner container from the outside in the event of a fire, where it suddenly leads to overpressure in the inner container, which can ultimately result in this inner container bursting and the radioactive substances escaping. This heat insulating material between the inner and outer container also prevents the decay heat of the radioactive substances from escaping to the outside. Therefore, the capacity of this container is very limited, because if the decay heat is released too much, heat accumulation could occur, which would lead to an inadmissible excess pressure in the inner container.
- the invention has for its object to remedy this and to achieve that the capacity of the container for radioactive substances is limited as little or not at all.
- a container of the type mentioned at the outset is characterized in that a cooling tube containing a circulable coolant is assigned to the inner container within the outer container, that a heat dissipation pipe which also contains the circulable coolant is arranged on the outer container and that the cooling pipe and the heat dissipation pipe are arranged above Communicate connecting lines at both pipe ends.
- the heat of decay of the radioactive substances in the inner container of the container can be transported to the outside and released through the heat insulating material due to the natural circulation of the circulating coolant. Nevertheless, the heat insulating material protects the inner container from sudden temperature increases in the event of a fire.
- a passage with a pressure relief valve or a rupture disk is provided on the cooling tube, on the heat dissipation tube and / or on the connecting lines in the wall thereof.
- this coolant can escape from the cooling pipe, the heat dissipation pipe and the connecting lines by actuating the pressure relief valve or blasting the rupture disc, because of the briefly excessive outside temperature, so that it cannot contribute to the heat transport from the outside to the inner container.
- the cooling tube, the heat dissipation tube and / or the connecting lines have a passage in the wall which is sealed with a solder, the melting temperature of which is lower than the melting temperature of the material of the cooling tube, the heat dissipation tube or the connecting lines. If the outside temperature rises, it will melt and burst this solder, so that in particular a liquid coolant can flow out of the cooling tube, the heat dissipation tube and the connecting lines and can no longer transport heat from the outside to the inner container.
- the capacity of the container according to the invention for radioactive substances is practically only determined by the volume of the inner container, which can be chosen to be of any size, it is advantageous if a body made of a material that absorbs neutrons is arranged in the interior of the inner container. This prevents the occurrence of a critical configuration of fissile radioactive substances in the inner container.
- the container according to FIG. 1 has an inner container 2 made of steel and an outer container 6 also made of steel.
- the inner container 2 is sealed gas and liquid-tight on all sides and stands on the inside of the base of the outer container 6 via support bodies 31.
- the outer container 6 is also gas and liquid-tight on all sides and closed at the top with a lid 7 which is screwed onto the outer container 6 with screws 8 is.
- heat insulating material 9 in the outer container 6, which can consist of glass wool or phenolic resin foam.
- the support body 31 also advantageously consist of a heat-poorly conductive heat insulating material such as ceramic.
- a helical cooling tube 10 made of copper is welded to the outside of the inner container 2. Furthermore, a heat-dissipation pipe 11 made of copper, which is also helical, is welded to the inside of the outer container 6. This heat dissipation tube can also be arranged on the outside of the outer container or embedded in the outer container.
- the upper end of the cooling tube 10 is connected to the upper end of the heat dissipation tube 11 with a connecting line 12 and the lower end of the cooling tube 10 to the lower end of the heat dissipating tube 11 with a connecting line 13, so that the cooling tube 10 and the heat dissipating tube 11 communicate with one another at both tube ends.
- the connecting lines 12 and 13 can also be pipes made of copper, but to facilitate assembly of the container, these connecting lines 12 and 13 can also consist of plastic hoses.
- the cooling tube 10, the heat dissipation tube 11 and the connecting lines 12 and 13 are filled with a circulating coolant, for example with a gaseous fluorinated hydrocarbon, with helium or with liquid water.
- a circulating coolant for example with a gaseous fluorinated hydrocarbon, with helium or with liquid water.
- the connecting line 13 designed as a tube has a rupture disk 15a in a passage 14 in the wall, which is shown in FIG. 2.
- a bushing 14 is provided in the connecting line 13 in the form of a tube, which, as shown in FIGS. 1 and 3, is sealed with a solder 15b made of a lead-tin alloy. While performing 14 2 with the rupture disc 15a in the interior of the outer container 6, the bushing 14 sealed with the solder 15b in FIGS.
- the cover 7 has a loading and unloading cover 16 above the loading and unloading pipe 4 and the ventilation pipe 5, which is screwed onto the cover 7 with screws 17. Furthermore, a steel tube 18, which is closed at both ends and is filled with boron carbide, which absorbs neutrons and prevents a critical configuration of fissile radioactive substances, is attached to the top 3 in the interior of the inner container 2. Finally, the cover 7 is also provided with a bushing 19, which in turn is closed with a rupture disk 20.
- the loading lid 16 is unscrewed from the lid 7 of the outer container 6.
- the loading and unloading pipe 4 and the ventilation pipe 5 are then connected to a loading station.
- the loading and unloading tube 4 and the ventilation tube 5 are uncoupled from the unloading station and sealed gas and liquid-tight with the caps 41 and 51, respectively.
- the loading lid 16 is screwed back onto the lid 7 of the outer container 6.
- the decay heat developed in the plutonium nitrate solution sets a natural circulation of the coolant in the cooling formed by the cooling tube 10, the heat dissipation tube 11 and the connecting lines 12 and 13 system in progress so that this decay heat is transported to the outer container 6 and radiated from it or removed by convection.
- the temperature on the outside of the outer container 6 increases suddenly.
- the heat insulating material 9 prevents heat from reaching the inner container 2 immediately from the outside and additionally heating the plutonium nitrate solution in this inner container 2.
- the coolant is heated in the heat dissipation pipe 11.
- the rupture disk 15a according to FIG. 2 bursts, while in the case of a liquid coolant the solder 15b according to FIGS. 1 and 3 melts due to the increased outside temperature.
- this coolant enters the interior of the outer container 6 and can escape to the outside through the bushing 19 if the bursting disk 20 bursts if the excess pressure is too high, while in the case of the liquid coolant, this immediately passes through the bushings 14 and 21 to the Outside of the outer container 6 flows. In both cases, heat can then no longer reach the inner container 2 via the cooling system formed by the cooling pipe 10, the heat dissipation pipe 11 and the connecting lines 12 and 13.
- either the inner container 2 of the container can be discharged or that from the cooling tube 10, the heat dissipation tube 11 and the Connecting lines 12 and 13, existing cooling system can be put back into operation by filling in coolant and closing the bushings 14.
- the cooling effect of the cooling system consisting of the cooling tube 10, the heat dissipation tube 11 and the connecting lines 12 and 13 can be increased even more if a cooling unit is connected to the connecting lines 12 and 13 or to the heat dissipation tube 11 at connecting pieces (not shown).
- the inner container 2 for shielding radioactive radiation can be surrounded by a radiation shield, which is also located in the outer container 6, but which is not shown in the drawing for the sake of clarity.
- the inner container can also be provided with a pressure relief valve opening into the outer container, which is preferably arranged in a passage in the wall on the upper part of the inner container.
- a pressure relief valve should also be understood to mean a capillary passage through the wall of the inner container, which is sealed with a solder, e.g. is sealed from a lead-tin alloy. If the temperature and pressure are too high, it melts and / or bursts e.g. the solder in the capillary feedthrough. Should the excess pressure in the inner container become impermissibly high, for example due to the formation of radiolysis gas, this excess pressure can be reduced by the pressure relief valve and the inner container can not burst.
- absorbent bodies for absorbing and / or absorbing substances which have escaped from the inner container into the outer container in the outer container outside the inner container.
- absorbent bodies are intended to absorb or absorb radioactive aerosol or radioactive liquid, which may escape from the inner container, for example through its pressure relief valve, and to neutralize it, if necessary.
- Such absorbent bodies can e.g. consist of silica gel, expanded mica or diatomaceous earth, which e.g. Contains calcium hydroxide, cyanide or alkaline cement finely divided as a neutralizing agent for nitric acid, in which plutonium is dissolved and which can be in the inner container. It can be advantageous if the absorbent bodies are designed in such a way that, if necessary, they can absorb, absorb or neutralize the entire amount of substance found in the inner container in a manner that is critical to criticism.
Landscapes
- Physics & Mathematics (AREA)
- Engineering & Computer Science (AREA)
- General Engineering & Computer Science (AREA)
- High Energy & Nuclear Physics (AREA)
- Packages (AREA)
- Filling Or Discharging Of Gas Storage Vessels (AREA)
Applications Claiming Priority (2)
Application Number | Priority Date | Filing Date | Title |
---|---|---|---|
DE3343166 | 1983-11-29 | ||
DE19833343166 DE3343166A1 (de) | 1983-11-29 | 1983-11-29 | Behaelter insbesondere fuer radioaktive substanzen |
Publications (3)
Publication Number | Publication Date |
---|---|
EP0143398A2 true EP0143398A2 (fr) | 1985-06-05 |
EP0143398A3 EP0143398A3 (en) | 1985-07-17 |
EP0143398B1 EP0143398B1 (fr) | 1987-09-09 |
Family
ID=6215571
Family Applications (1)
Application Number | Title | Priority Date | Filing Date |
---|---|---|---|
EP84113774A Expired EP0143398B1 (fr) | 1983-11-29 | 1984-11-14 | Récipient en particulier pour substances radioactives |
Country Status (6)
Country | Link |
---|---|
US (1) | US4672213A (fr) |
EP (1) | EP0143398B1 (fr) |
JP (1) | JPS61147199A (fr) |
BR (1) | BR8406038A (fr) |
CA (1) | CA1232088A (fr) |
DE (2) | DE3343166A1 (fr) |
Cited By (3)
Publication number | Priority date | Publication date | Assignee | Title |
---|---|---|---|---|
EP0269885A1 (fr) * | 1986-11-13 | 1988-06-08 | Siemens Aktiengesellschaft | Conteneur, en particulier pour des substances radioactives |
WO2000004558A1 (fr) * | 1998-07-16 | 2000-01-27 | British Nuclear Fuels Plc | Appareil de confinement de combustible |
FR2791805A1 (fr) * | 1999-03-30 | 2000-10-06 | Commissariat Energie Atomique | Installation d'entreposage de tres longue duree de produits calorifiques tels que des dechets nucleaires |
Families Citing this family (14)
Publication number | Priority date | Publication date | Assignee | Title |
---|---|---|---|---|
US4880989A (en) * | 1983-03-21 | 1989-11-14 | Mallinckrodt, Inc. | Shielding container for radioaerosol delivery apparatus |
US4747512A (en) * | 1987-06-19 | 1988-05-31 | Lo Kin K | Transportation packaging for liquids |
DE9005277U1 (de) * | 1990-05-09 | 1991-02-14 | Edelhoff Polytechnik Gmbh & Co, 58640 Iserlohn | Aufnahmeeinrichtung für vorzugsweise gefährdende Substanzen |
FR2724756B1 (fr) * | 1994-09-16 | 1996-12-27 | Robatel Slpi | Dispositif pour le refroidissement d'enceintes de confinement, notamment de silos de stockage de combustibles nucleaires irradies |
SE521224C2 (sv) * | 2001-01-29 | 2003-10-14 | Hans Georgii | Anordning för förvaring av värmeproducerande riskmaterial, i synnerhet kärnbränsle, och för en sådan anordning avsett kärl |
FR2835090B1 (fr) * | 2002-01-23 | 2005-08-05 | Commissariat Energie Atomique | Installation d'entreposage de tres longue duree de produits emettant un flux thermique eleve |
US6587536B1 (en) * | 2002-03-18 | 2003-07-01 | Holtec International, Inc. | Method and apparatus for maximizing radiation shielding during cask transfer procedures |
US7820870B2 (en) * | 2006-07-10 | 2010-10-26 | Holtec International, Inc. | Apparatus, system and method for facilitating transfer of high level radioactive waste to and/or from a pool |
US7786456B2 (en) * | 2006-10-11 | 2010-08-31 | Holtec International, Inc. | Apparatus for providing additional radiation shielding to a container holding radioactive materials, and method of using the same to handle and/or process radioactive materials |
JP4966214B2 (ja) * | 2008-01-21 | 2012-07-04 | 東京電力株式会社 | 使用済燃料の熱回収システム |
FR2944378B1 (fr) * | 2009-04-14 | 2011-06-10 | Tn Int | Dispositif de conditionnement pour le stockage et/ou entreposage d'un milieu liquide radioactif |
US8995604B2 (en) | 2009-11-05 | 2015-03-31 | Holtec International, Inc. | System, method and apparatus for providing additional radiation shielding to high level radioactive materials |
EP2899725B1 (fr) * | 2014-01-27 | 2018-04-25 | Urenco Limited | Contrôle de la température du matériau d'uranium dans une installation d'enrichissement d'uranium |
US11443862B2 (en) | 2020-04-01 | 2022-09-13 | Holtec International | Storage system for radioactive nuclear waste with pressure surge protection |
Citations (6)
Publication number | Priority date | Publication date | Assignee | Title |
---|---|---|---|---|
US2968734A (en) * | 1956-01-06 | 1961-01-17 | Martin Co | Device for the exposure of fluid to radiation |
US3113215A (en) * | 1961-02-27 | 1963-12-03 | Stanray Corp | Cask construction for radioactive material |
US3466444A (en) * | 1965-08-24 | 1969-09-09 | Edward Lead Co | Differentially vented carrying cask for radioactive materials |
US3851179A (en) * | 1974-02-05 | 1974-11-26 | Atomic Energy Commission | Shipping cask neutron and heat shield |
US3930166A (en) * | 1972-11-28 | 1975-12-30 | Robatel Slpi | Package for transporting or enclosing radioactive materials |
GB2087294A (en) * | 1980-10-31 | 1982-05-26 | Nuclear Power Co Ltd | Fuel element storage container |
Family Cites Families (6)
Publication number | Priority date | Publication date | Assignee | Title |
---|---|---|---|---|
US3046403A (en) * | 1959-04-17 | 1962-07-24 | Babcock & Wilcox Co | Device for the storage of a heat evolving material |
US3391280A (en) * | 1964-11-06 | 1968-07-02 | Nat Lead Co | Fire protection shield for radioactive shipping container |
DE1501340B2 (de) * | 1965-04-13 | 1971-04-29 | Allmanna Svenska Elektriska AB, Vasteras (Schweden) | Sicherheitsbehaelter fuer kernreaktoren |
US3666616A (en) * | 1970-01-07 | 1972-05-30 | Babcock & Wilcox Co | Vapor suppressing means for a nuclear reactor |
US4167968A (en) * | 1977-12-30 | 1979-09-18 | Babcock-Brown Boveri Reaktor Gmbh | Pressure vessel |
DE3143351A1 (de) * | 1980-10-31 | 1982-09-02 | Nuclear Power Co. Ltd., London | Aufnahmebehaelter und aufnahmeanordnung fuer nukleare brennelemente |
-
1983
- 1983-11-29 DE DE19833343166 patent/DE3343166A1/de not_active Withdrawn
-
1984
- 1984-11-14 EP EP84113774A patent/EP0143398B1/fr not_active Expired
- 1984-11-14 DE DE8484113774T patent/DE3466117D1/de not_active Expired
- 1984-11-27 CA CA000468660A patent/CA1232088A/fr not_active Expired
- 1984-11-28 US US06/675,515 patent/US4672213A/en not_active Expired - Fee Related
- 1984-11-28 BR BR8406038A patent/BR8406038A/pt unknown
- 1984-11-28 JP JP59251435A patent/JPS61147199A/ja active Pending
Patent Citations (6)
Publication number | Priority date | Publication date | Assignee | Title |
---|---|---|---|---|
US2968734A (en) * | 1956-01-06 | 1961-01-17 | Martin Co | Device for the exposure of fluid to radiation |
US3113215A (en) * | 1961-02-27 | 1963-12-03 | Stanray Corp | Cask construction for radioactive material |
US3466444A (en) * | 1965-08-24 | 1969-09-09 | Edward Lead Co | Differentially vented carrying cask for radioactive materials |
US3930166A (en) * | 1972-11-28 | 1975-12-30 | Robatel Slpi | Package for transporting or enclosing radioactive materials |
US3851179A (en) * | 1974-02-05 | 1974-11-26 | Atomic Energy Commission | Shipping cask neutron and heat shield |
GB2087294A (en) * | 1980-10-31 | 1982-05-26 | Nuclear Power Co Ltd | Fuel element storage container |
Cited By (6)
Publication number | Priority date | Publication date | Assignee | Title |
---|---|---|---|---|
EP0269885A1 (fr) * | 1986-11-13 | 1988-06-08 | Siemens Aktiengesellschaft | Conteneur, en particulier pour des substances radioactives |
US4836975A (en) * | 1986-11-13 | 1989-06-06 | Alkem Gmbh | Container, in particular for a radioactive substance |
WO2000004558A1 (fr) * | 1998-07-16 | 2000-01-27 | British Nuclear Fuels Plc | Appareil de confinement de combustible |
FR2791805A1 (fr) * | 1999-03-30 | 2000-10-06 | Commissariat Energie Atomique | Installation d'entreposage de tres longue duree de produits calorifiques tels que des dechets nucleaires |
WO2000060609A1 (fr) * | 1999-03-30 | 2000-10-12 | Commissariat A L'energie Atomique | Installation d'entreposage de tres longue duree de produits degageant de la chaleur tels que des dechets nucleaires |
US6802671B1 (en) | 1999-03-30 | 2004-10-12 | Commissariat A L'energie Atomique | Installation for very long term storage of heat-generating products such as nuclear waste |
Also Published As
Publication number | Publication date |
---|---|
CA1232088A (fr) | 1988-01-26 |
EP0143398A3 (en) | 1985-07-17 |
EP0143398B1 (fr) | 1987-09-09 |
DE3466117D1 (en) | 1987-10-15 |
US4672213A (en) | 1987-06-09 |
DE3343166A1 (de) | 1985-06-05 |
BR8406038A (pt) | 1985-08-27 |
JPS61147199A (ja) | 1986-07-04 |
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Legal Events
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