Various embodiments are disclosed of a canister for the disposal of hazardous radioactive waste in a borehole repository. The canister has a shell body containing the waste. In one embodiment, the canister is equipped with a removable lift adaptor that enables emplacement and removal of the canister in and from the borehole repository. A lid assembly at the top end of the shell body includes a shielded closure plug, a keyhole fitting to which the removable lift adaptor is attached to and detached from, a cover ring, and a threaded jam nut that secures and unsecures the cover ring and the lift adaptor to the keyhole fitting.
Described herein, are methods for providing a protective coating to a storage container for storing nuclear material, the method comprising depositing nickel particles on at least one surface of the substrate to produce the protective coating, wherein the nickel particles are deposited by cold spraying a composition comprising nickel particles and a carrier gas comprising nitrogen. In one aspect, the carrier gas consists essentially or consists only of nitrogen. The methods do not require pretreatment or modification of the nickel particles prior to cold spraying, which makes the methods described herein economically practical. The coatings produced by the methods described herein possess several advantageous properties including, but not limited to, high adhesion strength to the storage system and low porosity. The coatings produced by the methods described herein are effective against chemical attack such as, for example, CISCC.
B05D 1/12 - Application de matériaux en particules
B05B 7/14 - Appareillages de pulvérisation pour débiter des liquides ou d'autres matériaux fluides provenant de plusieurs sources, p. ex. un liquide et de l'air, une poudre et un gaz agencés pour projeter des matériaux en particules
A hazardous waste canister includes a housing that defines an interior volume configured to store nuclear waste, the housing configured to enclose the nuclear waste in a human-unoccupiable drillhole formed from a terranean surface into a subterranean formation; a support assembly positioned within the inner volume and configured to fill at least a portion of a gap between the housing and the enclosed nuclear waste; a lid assembly configured to couple to an open end of the housing to seal the inner volume; and a lift assembly coupled to the lid assembly and configured to engage a lifting device.
G21F 5/12 - Dispositifs obturateurs pour récipientsDispositions pour leur étanchéité
G21F 5/14 - Dispositifs spécialement adaptés à la manipulation de récipients ou de barils, p. ex. dispositifs de transport
G21F 5/10 - Dispositifs d'évacuation de chaleur spécialement adaptés à ces récipients, p. ex. utilisant une circulation de fluide ou des ailettes de refroidissement
G21F 5/008 - Récipients pour éléments combustibles
G21F 3/00 - Blindage caractérisé par sa forme physique, p. ex. granulés, ou forme du matériau
4.
Methods for cold spraying nickel particles on a substrate
Described herein, are methods for providing a protective coating to a storage container for storing nuclear material, the method comprising depositing nickel particles on at least one surface of the substrate to produce the protective coating, wherein the nickel particles are deposited by cold spraying a composition comprising nickel particles and a carrier gas comprising nitrogen. In one aspect, the carrier gas consists essentially or consists only of nitrogen. The methods do not require pretreatment or modification of the nickel particles prior to cold spraying, which makes the methods described herein economically practical. The coatings produced by the methods described herein possess several advantageous properties including, but not limited to, high adhesion strength to the storage system and low porosity. The coatings produced by the methods described herein are effective against chemical attack such as, for example, CISCC.
B05D 1/12 - Application de matériaux en particules
B05B 7/14 - Appareillages de pulvérisation pour débiter des liquides ou d'autres matériaux fluides provenant de plusieurs sources, p. ex. un liquide et de l'air, une poudre et un gaz agencés pour projeter des matériaux en particules
Described herein, are methods for providing a protective coating to a storage container for storing nuclear material, the method comprising depositing nickel particles on at least one surface of the substrate to produce the protective coating, wherein the nickel particles are deposited by cold spraying a composition comprising nickel particles and a carrier gas comprising nitrogen. In one aspect, the carrier gas consists essentially or consists only of nitrogen. The methods do not require pretreatment or modification of the nickel particles prior to cold spraying, which makes the methods described herein economically practical. The coatings produced by the methods described herein possess several advantageous properties including, but not limited to, high adhesion strength to the storage system and low porosity. The coatings produced by the methods described herein are effective against chemical attack such as, for example, CISCC.
B05B 7/14 - Appareillages de pulvérisation pour débiter des liquides ou d'autres matériaux fluides provenant de plusieurs sources, p. ex. un liquide et de l'air, une poudre et un gaz agencés pour projeter des matériaux en particules
42 - Services scientifiques, technologiques et industriels, recherche et conception
Produits et services
Electrolysis machines for generating hydrogen Adsorption apparatus for generating hydrogen Consulting and engineering for the demonstration and implementation of Hydrogen generation systems at nuclear power stations
10.
Thermal divider insert and method for spent nuclear fuel cask creating both air inlets and air outlets at the top of the overpack
Embodiments of a thermal divider insert for a dry storage, spent nuclear fuel cask are disclosed. The thermal divider insert enables safe storage of the hazardous nuclear material when one or more air inlets have been fully or partially blocked to an extent that insufficient air flows into the air inlets and through the cask for adequate cooling of the hazardous nuclear material. A concrete overpack contains a metal canister with the hazardous nuclear material. The overpack has an inside surface that is spaced from an outer surface of the canister to create an annular region that permits flow of air between the surfaces for cooling the canister. Air inlets near the bottom of the overpack communicate air from an outside into the annular region. Outlet vents near the top of the overpack communicate air from the annular region to the outside. The thermal divider insert extends through a respective outlet vent and into the annular region and establishes two separate and opposite air flows through the respective vent and the annular region when the overpack air inlets have been blocked.
G21F 5/10 - Dispositifs d'évacuation de chaleur spécialement adaptés à ces récipients, p. ex. utilisant une circulation de fluide ou des ailettes de refroidissement
G21F 5/008 - Récipients pour éléments combustibles
G21F 5/12 - Dispositifs obturateurs pour récipientsDispositions pour leur étanchéité
11.
Method for making containment cask for drum containing radioactive hazardous waste
A containment cask is disclosed for safely transporting and storing radioactive hazardous waste in a dry air environment. The cask comprises a single drum containing the radioactive hazardous waste, a sealed and shielded containment vessel containing the drum, and an outer container. The outer container can be in the form of an outer shield vessel (OSV) made from iron to provide further shielding. This outer container is appropriate for a drum having higher activity waste. The outer container can also be in the form of an overpack assembly that adds protection for atmospheric hazards, but adds little in terms of shielding. This outer container is appropriate for a drum having lower activity waste.
A container is designed to safely store radioactive debris. The container has an overpack having an elongated body extending between a top end and a bottom end. A basket is situated inside of the overpack. The basket has elongated canisters. Each of the canisters has an elongated body extending between a top end and a bottom end. At least one of the canisters has an insert with a plurality of elongated perforated tubes that contain radioactive debris. The perforations enable gas flow, primarily air, through the side wall to enable evaporation of liquid, primarily water, from the radioactive debris, by increasing the exposed surface area of the debris.
A container is designed to safely store radioactive debris. The container has an overpack having an elongated body extending between a top end and a bottom end. A basket is situated inside of the overpack. The basket has elongated canisters. Each of the canisters has an elongated body extending between a top end and a bottom end. At least one of the canisters has an insert with a plurality of elongated perforated tubes that contain radioactive debris. The perforations enable gas flow, primarily air, through the side wall to enable evaporation of liquid, primarily water, from the radioactive debris, by increasing the exposed surface area of the debris.
In one aspect, the disclosure relates to storage systems comprising a protective barrier to chemical attack, e.g. to chloride-induced stress corrosion cracking (CISCC). Moreover, the disclosed protective barriers can provide enhanced protection to or otherwise shield against general corrosion. In a further aspect, the disclosed protective barriers have minimal activity as catalysts for galvanic corrosion. The present disclosure further pertains to methods of applying the disclosed protective barriers to the disclosed storage systems. In various aspects, the disclosed storage systems are used for the storage of nuclear material. This abstract is intended as a scanning tool for purposes of searching in the particular art and is not intended to be limiting of the present disclosure.
G21F 9/22 - Moyens de se débarrasser des résidus liquides par stockage dans une cuve ou un autre récipient
G21F 5/015 - Récipients blindés portatifs ou transportables pour le stockage de sources radioactives, p. ex. supports de sources pour unités d'irradiationRécipients pour radio-isotopes
G21F 5/005 - Récipients pour déchets radioactifs solides, p. ex. pour le stockage final
G21F 5/002 - Récipients pour déchets radioactifs fluides
A storage apparatus is provided for dry storage of radioactive nuclear waste. The storage apparatus comprises a sealed canister containing the radioactive nuclear waste and an outer ventilated metal storage overpack (VMSO). The VMSO has a plurality of vents to enable ambient air flow through the VMSO and around the canister to thereby dissipate heat from the canister. The VMSO has a side wall having an inner metal layer and one or more sets of alternating layers. Each set includes a neutron absorbing layer adjacent to another metal layer so that neutron absorbing and metal layers alternate throughout the side wall.
G21F 5/005 - Récipients pour déchets radioactifs solides, p. ex. pour le stockage final
G21F 5/008 - Récipients pour éléments combustibles
G21F 5/10 - Dispositifs d'évacuation de chaleur spécialement adaptés à ces récipients, p. ex. utilisant une circulation de fluide ou des ailettes de refroidissement
G21F 5/12 - Dispositifs obturateurs pour récipientsDispositions pour leur étanchéité
A storage apparatus is provided for dry storage of radioactive nuclear waste. The storage apparatus comprises a sealed canister containing the radioactive nuclear waste and an outer ventilated metal storage overpack (VMSO). The VMSO has a plurality of vents to enable ambient air flow through the VMSO and around the canister to thereby dissipate heat from the canister. The VMSO has a side wall having an inner metal layer and one or more sets of alternating layers. Each set includes a neutron absorbing layer adjacent to another metal layer so that neutron absorbing and metal layers alternate throughout the side wall. The neutron absorbing layer or layers are designed to absorb neutron particles radiated from the radioactive nuclear waste and the metal layers are designed to absorb gamma particles radiated from the radioactive nuclear waste as well as radiated from the neutron absorbing layer or layers that result from reactions associated with absorption of neutron particles.
G21F 5/008 - Récipients pour éléments combustibles
G21F 5/10 - Dispositifs d'évacuation de chaleur spécialement adaptés à ces récipients, p. ex. utilisant une circulation de fluide ou des ailettes de refroidissement
A containment cask for safely transporting and storing radioactive hazardous waste in a dry air environment. The cask comprises a single drum containing the radioactive hazardous waste, a sealed and shielded containment vessel containing the drum, and an outer container. The outer container can be in the form of an outer shield vessel (OSV) made from iron to provide further shielding. This outer container is appropriate for a drum having higher activity waste. The outer container can also be in the form of an overpack assembly that adds protection for atmospheric hazards, but adds little in terms of shielding. This outer container is appropriate for a drum having lower activity waste.
A containment cask for safely transporting and storing radioactive hazardous waste in a dry air environment. The cask comprises a single drum containing the radioactive hazardous waste, a sealed and shielded containment vessel containing the drum, and an outer container. The outer container can be in the form of an outer shield vessel (OSV) made from iron to provide further shielding. This outer container is appropriate for a drum having higher activity waste. The outer container can also be in the form of an overpack assembly that adds protection for atmospheric hazards, but adds little in terms of shielding. This outer container is appropriate for a drum having lower activity waste.
Systems and methods of transferring nuclear fuel from fuel pools having size and/or weight limitations to a storage or transport cask are disclosed. A canister containing spent nuclear fuel is inserted into a transfer cask. A shielding sleeve is then placed around the transfer cask. A lifting device simultaneously lifts the transfer cask and the shielding sleeve over a storage cask and the spent fuel is transferred from the transfer cask to the storage or transport cask.
G21C 19/32 - Appareils pour enlever des objets ou matériaux radioactifs de l'aire de décharge du réacteur, p. ex. pour les porter à un emplacement de stockageAppareils pour manipuler des objets ou matériaux radioactifs à l'intérieur d'un emplacement de stockage ou les extraire de celui-ci
G21F 5/008 - Récipients pour éléments combustibles
A modular portable cask transfer (MPCT) facility is capable of transferring a canister containing spent nuclear fuel materials from or to a transportation cask respectively to or from a storage overpack. A transfer cask is utilized for the transfer. Telescoping legs enable movement of the transfer cask independent of the canister, which is moved using a hoist. Due to its modular configuration, the MPCT facility can be assembled, disassembled, and moved from one nuclear power plant to another.
G21F 5/14 - Dispositifs spécialement adaptés à la manipulation de récipients ou de barils, p. ex. dispositifs de transport
B66C 19/00 - Ponts roulants ou portiques fixes ou mobiles, portant un chariot ou un treuil mobile
G21C 19/32 - Appareils pour enlever des objets ou matériaux radioactifs de l'aire de décharge du réacteur, p. ex. pour les porter à un emplacement de stockageAppareils pour manipuler des objets ou matériaux radioactifs à l'intérieur d'un emplacement de stockage ou les extraire de celui-ci
A container is designed to safely store radioactive debris from, for example, a nuclear reactor meltdown, in water or air. The container, with preferably although not necessarily all metal parts, has an overpack having an elongated cylindrical body extending between a top end and a bottom end, a planar bottom part at the bottom end, an open top at the top end, and a circular planar lid mounted over the open top. A basket is situated inside of the overpack. The basket has a plurality of elongated cylindrical canisters that are in parallel along their lengths. Each of the canisters has an elongated cylindrical body extending between a top end and a bottom end, a planar bottom part at the bottom end, an open top at the top end, and a circular planar lid mounted over the open top.
G21F 5/015 - Récipients blindés portatifs ou transportables pour le stockage de sources radioactives, p. ex. supports de sources pour unités d'irradiationRécipients pour radio-isotopes
G21C 19/40 - Dispositions pour prévenir l'apparition de conditions critiques, p. ex. pendant le stockage
A container is designed to safely store radioactive debris from, for example, a nuclear reactor meltdown, in water or air. The container, with preferably although not necessarily all metal parts, has an overpack having an elongated cylindrical body extending between a top end and a bottom end, a planar bottom part at the bottom end, an open top at the top end, and a circular planar lid mounted over the open top. A basket is situated inside of the overpack. The basket has a plurality of elongated cylindrical canisters that are in parallel along their lengths. Each of the canisters has an elongated cylindrical body extending between a top end and a bottom end, a planar bottom part at the bottom end, an open top at the top end, and a circular planar lid mounted over the open top.
A container is designed to safely store radioactive debris from, for example, a nuclear reactor meltdown, in water or air. The container, with preferably although not necessarily all metal parts, has an overpack having an elongated cylindrical body extending between a top end and a bottom end, a planar bottom part at the bottom end, an open top at the top end, and a circular planar lid mounted over the open top. A basket is situated inside of the overpack. The basket has a plurality of elongated cylindrical canisters that are in parallel along their lengths. Each of the canisters has an elongated cylindrical body extending between a top end and a bottom end, a planar bottom part at the bottom end, an open top at the top end, and a circular planar lid mounted over the open top.
In one embodiment, a system and method for dry storage comprises removing spent fuel rods from their fuel rod assemblies and placing the freed fuel rods in a storage cell of a dry storage canister with a high packing density and without a neutron absorber material present.
G21C 19/00 - Dispositions pour le traitement, pour la manipulation, ou pour faciliter la manipulation, du combustible ou d'autres matériaux utilisés à l'intérieur du réacteur, p. ex. à l'intérieur de l'enceinte sous pression
G21F 5/012 - Râteliers pour éléments combustibles dans le récipient
G21F 5/10 - Dispositifs d'évacuation de chaleur spécialement adaptés à ces récipients, p. ex. utilisant une circulation de fluide ou des ailettes de refroidissement
29.
System and method to control spent nuclear fuel temperatures
Systems and methods of the disclosure are directed toward removing moisture from, and controlling the temperature of, spent nuclear fuel stored in spent fuel containers and the containers themselves. A vacuum system may remove vapor and gas from the container to reduce pressure and stimulate moisture evaporation. The potentially radioactive gas exiting the spent fuel container can also be transported to a radioactive waste gas system. A non-reactive gas is then circulated through a circulation path, which is communicatively coupled to a spent fuel container. The non-reactive gas can absorb heat and/or moisture from the spent fuel stored within the spent fuel container. Accordingly, heat can be removed by a heat exchanger coupled to the circulation path. Condensate moisture can also be removed from the circulation path.
G21C 19/00 - Dispositions pour le traitement, pour la manipulation, ou pour faciliter la manipulation, du combustible ou d'autres matériaux utilisés à l'intérieur du réacteur, p. ex. à l'intérieur de l'enceinte sous pression
G21F 5/10 - Dispositifs d'évacuation de chaleur spécialement adaptés à ces récipients, p. ex. utilisant une circulation de fluide ou des ailettes de refroidissement
G21F 5/00 - Récipients blindés portatifs ou transportables
A transfer cask system for cooling spent nuclear fuel during the transfer from a spent nuclear fuel pool to a storage or transfer cask is disclosed. A canister containing spent nuclear fuel is inserted into a transfer cask. The transfer cask includes spacing components which define an annular region between the transfer cask and the canister. The transfer cask includes air inlets near a bottom end that permit air to flow through the defined annular region and exit at the open top of the transfer cask, thereby cooling the fuel within the canister. The transfer cask further comprises a neutron shield configured to absorb additional heat and shield radiation that may be generated within the canister. The transfer cask includes a transfer door that can open and close and has support rails that can support a spent nuclear fuel canister located in the transfer cask.
G21F 5/10 - Dispositifs d'évacuation de chaleur spécialement adaptés à ces récipients, p. ex. utilisant une circulation de fluide ou des ailettes de refroidissement
G21F 5/008 - Récipients pour éléments combustibles
31.
SYSTEMS AND METHODS FOR TRANSFERRING SPENT NUCLEAR FUEL FROM WET STORAGE TO DRY STORAGE
Systems and methods of transferring nuclear fuel from fuel pools having size and/or weight limitations to a storage or transport cask are disclosed. A canister containing spent nuclear fuel is inserted into a transfer cask. A shielding sleeve is then placed around the transfer cask. A lifting device simultaneously lifts the transfer cask and the shielding sleeve over a storage cask and the spent fuel is transferred from the transfer cask to the storage or transport cask.
G21C 19/00 - Dispositions pour le traitement, pour la manipulation, ou pour faciliter la manipulation, du combustible ou d'autres matériaux utilisés à l'intérieur du réacteur, p. ex. à l'intérieur de l'enceinte sous pression
G21C 19/32 - Appareils pour enlever des objets ou matériaux radioactifs de l'aire de décharge du réacteur, p. ex. pour les porter à un emplacement de stockageAppareils pour manipuler des objets ou matériaux radioactifs à l'intérieur d'un emplacement de stockage ou les extraire de celui-ci
32.
Systems and methods for transferring spent nuclear fuel from wet storage to dry storage
Systems and methods of transferring nuclear fuel from fuel pools having size and/or weight limitations to a storage or transport cask are disclosed. A canister containing spent nuclear fuel is inserted into a transfer cask. A shielding sleeve is then placed around the transfer cask. A lifting device simultaneously lifts the transfer cask and the shielding sleeve over a storage cask and the spent fuel is transferred from the transfer cask to the storage or transport cask.
G21C 19/00 - Dispositions pour le traitement, pour la manipulation, ou pour faciliter la manipulation, du combustible ou d'autres matériaux utilisés à l'intérieur du réacteur, p. ex. à l'intérieur de l'enceinte sous pression
G21F 5/008 - Récipients pour éléments combustibles
G21C 19/32 - Appareils pour enlever des objets ou matériaux radioactifs de l'aire de décharge du réacteur, p. ex. pour les porter à un emplacement de stockageAppareils pour manipuler des objets ou matériaux radioactifs à l'intérieur d'un emplacement de stockage ou les extraire de celui-ci
In one embodiment, a system and method for dry storage comprises removing spent fuel rods from their fuel rod assemblies and placing the freed fuel rods in a storage cell of a dry storage canister with a high packing density and without a neutron absorber material present.
G21C 19/00 - Dispositions pour le traitement, pour la manipulation, ou pour faciliter la manipulation, du combustible ou d'autres matériaux utilisés à l'intérieur du réacteur, p. ex. à l'intérieur de l'enceinte sous pression
G21F 5/012 - Râteliers pour éléments combustibles dans le récipient
G21F 5/10 - Dispositifs d'évacuation de chaleur spécialement adaptés à ces récipients, p. ex. utilisant une circulation de fluide ou des ailettes de refroidissement
34.
SYSTEMS AND METHODS FOR DRY STORAGE AND/OR TRANSPORT OF CONSOLIDATED NUCLEAR SPENT FUEL RODS
In one embodiment, a system and method for dry storage comprises removing spent fuel rods from their fuel rod assemblies and placing the freed fuel rods in a storage cell of a dry storage canister with a high packing density and without a neutron absorber material present. Nuclear fuel assemblies for powering nuclear reactors generally comprise large numbers of fuel rods that are contained in discrete fuel rod assemblies.
G21C 19/32 - Appareils pour enlever des objets ou matériaux radioactifs de l'aire de décharge du réacteur, p. ex. pour les porter à un emplacement de stockageAppareils pour manipuler des objets ou matériaux radioactifs à l'intérieur d'un emplacement de stockage ou les extraire de celui-ci
35.
SYSTEM AND METHOD FOR INTEGRATION OF WET AND DRY NUCLEAR FUEL STORAGE
Systems and methods of loading and/or removing spent nuclear fuel from a spent nuclear fuel pool are disclosed. A spent fuel basket compatible with a dry storage and/or transport system is disposed in a spent nuclear fuel pool. At least one spent fuel assembly is loaded in one of a plurality of chambers associated with the spent fuel basket. The spent fuel basket is inserted into a spent fuel canister. The spent fuel canister is loaded into a transfer cask. The spent fuel canister is then transferred from the transfer cask to a storage cask or a transport cask, which can be sealed and stored on-site or in an off-site storage facility.
40 - Traitement de matériaux; recyclage, purification de l'air et traitement de l'eau
Produits et services
Providing information in the field of nuclear power generation, including satellite imagery and other facility information, to nuclear industry subscribers via the Internet
40 - Traitement de matériaux; recyclage, purification de l'air et traitement de l'eau
Produits et services
Providing information in the field of nuclear power generation, including satellite imagery and other facility information, to nuclear industry subscribers via the Internet
39.
Apparatuses and methods for mechanical shielding and cooling
A transport or storage cask comprises a cask body, a modular thermal conducting and shielding system and a mechanical attachment. The modular thermal conducting and shielding system includes a modular fin and a modular neutron shield. The mechanical attachment retains the modular thermal conducting and shielding system to the cask body. The modular fin is disposed between the modular neutron shield and the cask body. The modular fin is capable of dissipating thermal energy from the cask body.
G21C 19/00 - Dispositions pour le traitement, pour la manipulation, ou pour faciliter la manipulation, du combustible ou d'autres matériaux utilisés à l'intérieur du réacteur, p. ex. à l'intérieur de l'enceinte sous pression
40.
Apparatus and methods for achieving redundant confinement sealing of a spent nuclear fuel canister
Disclosed are the apparatus and methods for closing a canister that stores and transports spent nuclear fuel. In one embodiment, the canister includes a canister shell that includes an open end. A closure lid is inserted within the open end of the canister shell. The closure lid engages the open end of the canister shell to provide a weld area that is substantially on the outer circumference of the closure lid. The weld area includes a first weld layer and a second weld layer. The first weld layer welds the closure lid to the canister shell at the weld area and closes the canister. The second weld layer also welds the closure lid to the canister shell at the weld area, providing a redundant closure seal, and is disposed substantially on top of the first weld layer. The method for closing the canister is provided herein.
G21C 13/00 - Enceintes sous pressionEnceintes d'enveloppeEnveloppes en général
G21C 19/00 - Dispositions pour le traitement, pour la manipulation, ou pour faciliter la manipulation, du combustible ou d'autres matériaux utilisés à l'intérieur du réacteur, p. ex. à l'intérieur de l'enceinte sous pression
41.
Container and method for storing or transporting spent nuclear fuel
Disclosed are apparatus and methods for storing or transporting spent nuclear fuel. In one embodiment, a container for storing spent nuclear fuel comprises a plurality of elongated tubes that receives spent nuclear fuel rods. Each tube has four sidewalls and four corners defining a rectangular cross section. The plurality of tubes is arranged in an alternating pattern. An attachment means attaches together the plurality of tubes at the corners so that two adjacent sidewalls of adjacent tubes are substantially aligned.
G21C 19/00 - Dispositions pour le traitement, pour la manipulation, ou pour faciliter la manipulation, du combustible ou d'autres matériaux utilisés à l'intérieur du réacteur, p. ex. à l'intérieur de l'enceinte sous pression
G21C 19/06 - Moyens pour supporter ou emmagasiner des éléments combustibles ou des éléments de commande
G21F 5/12 - Dispositifs obturateurs pour récipientsDispositions pour leur étanchéité
