EP0004241B1 - Dispositif de jonction entre un conteneur et une enceinte de déchargement - Google Patents

Dispositif de jonction entre un conteneur et une enceinte de déchargement Download PDF

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Publication number
EP0004241B1
EP0004241B1 EP79400152A EP79400152A EP0004241B1 EP 0004241 B1 EP0004241 B1 EP 0004241B1 EP 79400152 A EP79400152 A EP 79400152A EP 79400152 A EP79400152 A EP 79400152A EP 0004241 B1 EP0004241 B1 EP 0004241B1
Authority
EP
European Patent Office
Prior art keywords
closure
container
seat
plug
ring
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
Application number
EP79400152A
Other languages
German (de)
English (en)
French (fr)
Other versions
EP0004241A1 (fr
Inventor
René Guilloteau
Jacques Segui
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.)
Commissariat a lEnergie Atomique et aux Energies Alternatives CEA
Original Assignee
Commissariat a lEnergie Atomique CEA
Priority date (The priority date 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 date listed.)
Filing date
Publication date
Application filed by Commissariat a lEnergie Atomique CEA filed Critical Commissariat a lEnergie Atomique CEA
Publication of EP0004241A1 publication Critical patent/EP0004241A1/fr
Application granted granted Critical
Publication of EP0004241B1 publication Critical patent/EP0004241B1/fr
Expired legal-status Critical Current

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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
    • G21F5/06—Details of, or accessories to, the containers
    • G21F5/12—Closures for containers; Sealing arrangements
    • 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
    • G21F7/00—Shielded cells or rooms
    • G21F7/005—Shielded passages through walls; Locks; Transferring devices between rooms

Definitions

  • the invention relates to a junction device between a transport container and a horizontal wall of an unloading enclosure, usable in particular for carrying out the unloading of lead containers in which were loaded irradiated nuclear fuel elements after combustion in nuclear reactors .
  • This device can be used in particular for the dry transfer of fuel elements or nuclear waste in a reprocessing plant.
  • the unloading of irradiated fuel elements from such containers is generally carried out by the wet method, according to the process known as "unloading in a swimming pool".
  • This known method makes it possible to fairly satisfactorily resolve certain radioactive contamination problems liable to arise during unloading operations.
  • it has a certain number of drawbacks. It indeed comprises a complex succession of operations, a significant part of which is inherent in the use of the wet process. This is particularly the case with the operations of fitting and removing protective skirts, the contents of which must be coated during their stay in the pool, as well as rinsing operations with high pressure water and operations decontamination carried out by manual wiping of wet parts.
  • Unloading in a swimming pool also involves the use of very important equipment, such as the swimming pools themselves and their equipment, protective skirts, and an extremely extensive network of pipes, the cumulative contamination of which poses problems. Due to the number and d--, complexity of the operations, as well as the importance of the equipment, the known wet methods require a considerable implantation surface. All of these factors make it more difficult and more complex to control the spread of radioactive contamination and thus tend to negate to some extent the benefits expected in this area of wet processes.
  • This device has the disadvantage of not associating a perfect seal between the two containers, especially when the two covers are joined together to be brought back into the first container.
  • the object of the invention is precisely to create a device for the dry unloading of containers used for the transport of radioactive substances, a device which, while making it possible to greatly simplify the operating process compared to known methods and correspondingly reduce the labor costs, container downtime and, in general, investment and operating costs, nevertheless achieves strict containment of contamination, thus ensuring full safety of personnel even in the event that operations require close intervention.
  • the device is designed to allow, as simply as possible, the possible implementation of remote control devices allowing staff to perform the various operations remotely with absolute security.
  • this remote control installation is not part of the present invention which is limited to the device proper, the constitution and the methods of use of which will be explained below.
  • the invention therefore relates to a dis positive to allow the dry unloading of containers used for the transport of radioactive substances, in particular lead containers containing nuclear fuels.
  • the invention more specifically relates to a sealed junction device between an upper opening of a container provided with a plug (2) and a lower opening of an unloading enclosure provided with a cover (17), the plug (2) and the cover (17) which can be brought together to be brought into the enclosure, characterized in that it further comprises a protective crown (16, 16 ") disposed at the top of the container, between the plug (2) and the cover (17).
  • FIGS. 1 and 2 The "container”, known per se and not forming part of the present invention, is shown in a very simplified and schematic manner in FIGS. 1 and 2. It essentially consists of a steel tank of circular cross-section shown in FIG. 1 with its axis of revolution 0-0 vertical, the lower part of this tank being closed by a solid bottom 1 and its upper part by a plug 2, also massive, placed on a crown 3 and held in place by a fixing flange 4 screwed onto the crown 3, the side wall of the composite tank being constituted on its internal face by a thin steel ferrule 5 and on its external face by a thick steel ferrule 6, a thickness of lead 7 being interposed between the ferrules 5 and 6.
  • ferrules 5 and 6 are integral on the one hand with the base 1, on the other hand with the crown 3, the ferrule 5 being in particular welded with these parts in a leaktight manner, and at least one seal ensuring sealing the plug 2 with respect to the crown 3.
  • a screwed sealing tape 8 with the interposition of a seal, on the upper face of the crown 3, completes the closure of the container.
  • a lateral external structure 9, enveloping the ferrule 6, essentially comprises means facilitating the evacuation of the heat produced within the internal cavity of the container by the radioactive substances contained therein (and which are not shown in the drawings) .
  • Trunnions 10, usually four in number at the top of the container and two in number on the bottom, allowing handling. In Fig. 1, the lower pin 10 on the left has been removed to make the container relief valve 11 visible.
  • the container is further protected by a lower cover 12 and an upper cover 13 made of a shock absorbing material.
  • the container When the container arrives at the unloading workshops, it is stripped of the protective accessories with which it was provided during transport, namely the upper and lower covers 12 and 13, as well as the sealing tape 8.
  • the upper part of the container is in the form shown very schematically in FIG. 3..
  • claws 14 Fixed on the upper face of the plug 2 and allowing the handling thereof. For reasons of clarity, these claws 14 had not been shown in FIG. 1, executed on a smaller scale.
  • FIG. 4 similar to FIG. 3, the plug fixing flange 4 has been unscrewed and removed and an adapter ring 15 has been put in place as well as a plug protection ring 16 2.
  • This adapter ring 15 and the ring protection 16 of the plug form part of the device according to the invention.
  • Fig. 5a we find the constituent parts of the container shown in the. Fig. 4, namely the side envelopes 3 and 9. the plug 2 with its claws 14, the adapter ring 15 and the ring 16 for protecting the plug 2;
  • This assembly was brought under a cover 17 and a cover seat 18, then centered and lifted until the upper face of the adaptation crown 15 and the upper face of the crown 16 for protecting the plug 2 are respectively in contact with the underside of the seal seat 18 and of the underside of the seal 17.
  • the seal 17 then rests on its seat 18 and the latter is tightly connected to a floor 19, this sealed connection by means of, on the one hand a hydraulic seal 20, on the other hand of bellows 21 which allow a certain degree of mobility in the vertical direction between the seal seat 18 and the floor 19 without the Tightness of the connection between this seat and this floor is compromised.
  • a gripping device designated as a whole by 22 and which essentially comprises a vertical circular barrel 23, coaxial with the cover 17 which it crosses inside a sheath 24.
  • This sheath 24 is held on the barrel 23 between a set of claws 25 fixed to the upper end of this barrel and a portion of larger diameter 23 ′ forming the lower end of the barrel 23.
  • the sleeve 24 can move slightly in the vertical direction relative to the cover 17 thanks to the bellows 27, which, during this movement maintains the seal between the sheath 24 and the cover 17.
  • claws 28 are fixed claws 28, regularly distributed around the axis 0-0, which is then common to the container and at the seal. These claws can engage, as will be seen below with the claws 14 fixed on the cap 2 of the container and which are also regularly distributed around the axis 0-0.
  • FIG. 6 is an enlarged reproduction of FIG. 5a.
  • the gripping device 22 which has just been described, has not been reproduced in FIG. 6, on which, however, details are not shown in FIG. 5a.
  • Fig. 6 shows in particular that the cover 17 has an added crown 17 'and that the cover seat 18 has an added crown 18', the crowns 17 'and 18' being respectively held by screwing on the cover and the seat.
  • the seal 29 Between the added crown 17 'and the cover 17 are the seal 29.
  • the seals 30 and 31 Between this same added crown 17' and the seat of the cover are the seals 30 and 31.
  • Between the added crown 18 'and the seat seal 18 is the seal 32.
  • Between the adapter ring 15 and the container 3 as well as the seal seat 18 are seals 33 and 34 respectively. Between the plug 2 and the container 3 is seal 35.
  • annular cavity 38 which can be supplied from the outside from the cell J, by at least one orifice 39, and which, via numerous channels 40 distributed over the periphery, is in communication with the space 41 between the cover and its seat.
  • This same space 41 is in communication, via at least one channel 42, with at least one orifice 43 opening into the upper cell S.
  • Fig. 7 shows a funnel, designated as a whole by 44, introduced into the opening of the lid seat 18 and of the adapter ring 15, and whose horizontal upper edge 45 is supported on the lid seat 18.
  • This funnel is double-walled 46 ′, 46 "with consequently an internal space 47 connected in its upper part to at least one suction device (not shown) by at least one tube 48.
  • Ports 49. formed in the internal wall 46 "from the funnel 44, allow, when the suction device is working, to suck the air - and the dust it holds in suspension - in the central area of the funnel 44.
  • a flange 50 At the lower end of the funnel 44 is provided.
  • a shutter base 51 can be placed at the lower end of the funnel 44.
  • the device according to the invention comprises the assembly formed by the adapter ring 15, the cap protection ring 16, the cover 17, the cover seat 18, the funnel 44, and comprises, at the same time time that these main parts all the ancillary equipment - gripping devices, seals, pipes, ... - assigned to each of these main parts and which have been described above.
  • the container is then in the state shown in FIG. 4, and it can no longer be moved except by maintaining its vertical axis, at least approximately, the plug 2 being held in place by its own weight, to which is added that of its protective crown 16.
  • volume a With regard to the volume a), it is planned to treat it when the different parts, after closing the container, are still in the respective positions shown in FIG. 7, that is to say before removing the closed container.
  • This treatment is carried out by injecting, via pipes (not shown) tightly connected to the orifices 39, a fluid in the circuit constituted by this orifice 39, the cavity 38, the channels 40, the volume 41, the channels 42 and pipes connected in a leaktight manner to the orifices 43, a fluid which may be a gas or a liquid.
  • volume a) or 41 If it is a gas or a fluid, the circulation of this fluid according to the arrows F will be at the highest possible speed so as to obtain a decontamination of the volume a) or 41 by an effect of washing and rinsing entraining the radioactive particles in an area far from cell J where they will no longer present a danger.
  • a viscous liquid it may be a special grease, forced into the circuit in the direction of the arrows F and whose role will be to close this circuit and in particular the volume a) or 41 while coating the radioactive particles and tending to move them away from the J cell.
  • volume a) or 41 will be filled with uncontaminated fat.
  • a sheet metal receptacle 52 can be placed under the cover and its seat when there is no container during unloading (see Fig. 8).
  • volume b With regard to volume b, the radioactive contamination which may have entered it remains confined in this sealed volume, and since the crowns 15 and 16 remain assembled during their removal, the assembly which they form can be transported without risk to propagate the contamination to a specialized workshop where the crowns 15 and 16 will be subjected to conventional decontamination treatments.
  • volume c the dimensions of which are extremely small, must be decontaminated "in situ”.
  • the combination formed by the double bellows 21 and the hydraulic seal 20 also allows an effective fight against the spread of contamination.
  • the use of a double bellows 21 allows, by a vacuum connection - normally closed by a tight plug 21 '- located between the two individual bellows, to test the tightness of these.
  • the presence of the hydraulic seal also makes it possible to keep the space existing between this seal and the bellows out of contamination and thus to proceed without risk to the replacement of the bellows if they are defective.
  • the hydraulic seal 20 is provided with devices known per se (for example a constant level supply) to preserve its effectiveness in all circumstances.
  • the device according to the invention makes it possible to satisfactorily avoid the propagation of radioactive contamination during operations related to dry unloading.
  • this device makes it possible, to a large extent, to handle containers of different types and in particular of different dimensions. If the device as used according to FIG. 5a corresponds to the maximum dimeter of the containers capable of being treated, FIG. 5'a shows how this device can be used for containers with smaller diameters. Only the shapes of the adaptation and protection crowns will have to be modified somewhat, the protection crown having in particular a diametral section which instead of being rectangular as in FIG. 5a, will have, in the 16 "version according to FIG. 5 'has a square shape, and the adapter ring, in its 15" version, being modified correspondingly.

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  • Physics & Mathematics (AREA)
  • Engineering & Computer Science (AREA)
  • General Engineering & Computer Science (AREA)
  • High Energy & Nuclear Physics (AREA)
  • Closures For Containers (AREA)
  • Refuse Receptacles (AREA)
  • Sealing Of Jars (AREA)
  • Pressure Vessels And Lids Thereof (AREA)
EP79400152A 1978-03-09 1979-03-08 Dispositif de jonction entre un conteneur et une enceinte de déchargement Expired EP0004241B1 (fr)

Applications Claiming Priority (2)

Application Number Priority Date Filing Date Title
FR7806821A FR2419568A1 (fr) 1978-03-09 1978-03-09 Dispositif de jonction entre un conteneur et une enceinte de dechargement
FR7806821 1978-03-09

Publications (2)

Publication Number Publication Date
EP0004241A1 EP0004241A1 (fr) 1979-09-19
EP0004241B1 true EP0004241B1 (fr) 1981-10-14

Family

ID=9205566

Family Applications (1)

Application Number Title Priority Date Filing Date
EP79400152A Expired EP0004241B1 (fr) 1978-03-09 1979-03-08 Dispositif de jonction entre un conteneur et une enceinte de déchargement

Country Status (6)

Country Link
US (1) US4310034A (enrdf_load_stackoverflow)
EP (1) EP0004241B1 (enrdf_load_stackoverflow)
JP (1) JPS54133298A (enrdf_load_stackoverflow)
DE (1) DE2960962D1 (enrdf_load_stackoverflow)
ES (1) ES478383A1 (enrdf_load_stackoverflow)
FR (1) FR2419568A1 (enrdf_load_stackoverflow)

Families Citing this family (19)

* Cited by examiner, † Cited by third party
Publication number Priority date Publication date Assignee Title
FR2625023B2 (fr) * 1978-03-09 1990-04-20 Commissariat Energie Atomique Dispositif de jonction entre un conteneur de transport et une paroi horizontale d'une enceinte de dechargement
DE3172191D1 (en) * 1980-07-01 1985-10-17 Contraves Ag Rigid coupling between an axle and the coding disc of an observation periscope
DE3024979C2 (de) * 1980-07-02 1984-02-02 Transnuklear Gmbh, 6450 Hanau Verfahren zur Herstellung einer eng anliegenden Innenauskleidung für Transport und/oder Lagerbehälter
JPS6038559Y2 (ja) * 1982-06-02 1985-11-18 日立造船株式会社 密封容器における蓋開閉装置
US4828789A (en) * 1984-02-03 1989-05-09 Westinghouse Electric Corp. Reactor vessel head permanent shield
US4636645A (en) * 1984-10-31 1987-01-13 Westinghouse Electric Corp. Closure system for a spent fuel storage cask
DE3440277C1 (de) * 1984-11-03 1986-05-22 Siempelkamp Gießerei GmbH & Co, 4150 Krefeld Verfahren zum Einbringen von radioaktiven Abfaellen in einen Schmelzofen und Vorrichtung zur Durchfuehrung des Verfahrens
FR2582139B1 (fr) * 1985-05-15 1989-11-24 Mediterranee Const Navales Ind Dispositif de transport, de positionnement et d'accostage d'un conteneur sous une fosse de chargement dans une installation nucleaire
FR2642217B1 (fr) * 1989-01-25 1991-05-03 Framatome Sa Dispositif d'etancheite pour une colonne d'instrumentation traversant le couvercle d'une cuve de reacteur nucleaire a eau sous pression
DE3905362A1 (de) * 1989-02-22 1990-08-23 Noell Gmbh Andockeinrichtung fuer radioaktive stoffe aufnehmende behaelter an einer schleuse
FR2666442B1 (fr) * 1990-09-05 1992-10-16 Commissariat Energie Atomique Machine de remplacement de portes d'acces a des zones irradiees, et utilisation d'une telle machine.
US5319686A (en) * 1993-07-30 1994-06-07 Newport News Shipbuilding And Dry Dock Company Dry transfer of spent nuclear rods for transporation
US5406600A (en) * 1993-10-08 1995-04-11 Pacific Nuclear Systems, Inc. Transportation and storage cask for spent nuclear fuels
JPH0824443A (ja) * 1994-07-05 1996-01-30 Autoplax Corp 軌道ディスプレー
FR2725188B1 (fr) * 1994-10-04 1996-10-25 Commissariat Energie Atomique Systeme d'accrochage d'un fut a une paroi d'enceinte
FR2833745B1 (fr) * 2001-12-14 2004-10-01 Becton Dickinson France Dispositif de protection pour enceinte sterile
FR2868590B1 (fr) * 2004-04-02 2006-06-09 Cogema Dispositif d'accostage etanche d'enceintes mobiles de differents diametres
EP2824669B1 (de) * 2013-07-10 2017-08-30 GNS Gesellschaft für Nuklear-Service mbH Brennstabköcher
FR3060192B1 (fr) * 2016-12-09 2019-05-17 Tn International Emballage de transport et/ou d'entreposage de matieres radioactives comprenant un systeme de communication fluidique ameliore entre l'interieur et l'exterieur de l'enceinte de confinement

Family Cites Families (7)

* Cited by examiner, † Cited by third party
Publication number Priority date Publication date Assignee Title
FR1452629A (fr) * 1965-04-16 1966-04-15 Kernforschung Gmbh Ges Fuer Dispositif de fermeture étanche aux gaz pour ouvertures de branchement de réservoirs ou analogues, et installation pourvue dudit dispositif ou similaire
FR1539845A (fr) * 1967-07-24 1968-09-20 Lyonnaise De Plomberie Ind Soc Perfectionnements aux dispositifs d'obturation associés aux portes d'introduction etd'évacuation des enceintes à atmosphère contaminée
FR2040616A5 (enrdf_load_stackoverflow) * 1969-04-04 1971-01-22 Commissariat Energie Atomique
DE2047538C3 (de) * 1970-09-26 1973-09-13 Gesellschaft Fuer Kernforschung Mbh, 7500 Karlsruhe Gasdichter Verschluß für zwei aneinander ankoppelbare Öffnungen zweier Behälter
CH529425A (de) * 1971-03-25 1972-10-15 Bbc Brown Boveri & Cie Brennelement-Wechselmaschine
US3765549A (en) * 1971-10-21 1973-10-16 Transfer Systems Apparatus and method for loading nuclear fuel into a shipping cask without immersion in a pool
US3838289A (en) * 1972-08-29 1974-09-24 Gilbert Associates Radioactive waste filter removal system

Also Published As

Publication number Publication date
FR2419568B1 (enrdf_load_stackoverflow) 1980-08-29
ES478383A1 (es) 1979-12-16
US4310034A (en) 1982-01-12
EP0004241A1 (fr) 1979-09-19
DE2960962D1 (en) 1981-12-24
JPS54133298A (en) 1979-10-16
FR2419568A1 (fr) 1979-10-05
JPS648318B2 (enrdf_load_stackoverflow) 1989-02-13

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