EP0042483B1 - Procédé et dispositif pour le stockage final d'éléments de construction de longue radioactivité - Google Patents

Procédé et dispositif pour le stockage final d'éléments de construction de longue radioactivité Download PDF

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Publication number
EP0042483B1
EP0042483B1 EP81103493A EP81103493A EP0042483B1 EP 0042483 B1 EP0042483 B1 EP 0042483B1 EP 81103493 A EP81103493 A EP 81103493A EP 81103493 A EP81103493 A EP 81103493A EP 0042483 B1 EP0042483 B1 EP 0042483B1
Authority
EP
European Patent Office
Prior art keywords
coil body
container
shaft
opening
screening
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
EP81103493A
Other languages
German (de)
English (en)
Other versions
EP0042483A1 (fr
Inventor
Günther Dannehl
Walter Haase
Günter Zeitzschel
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.)
Kraftwerk Union AG
Original Assignee
Kraftwerk Union AG
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 Kraftwerk Union AG filed Critical Kraftwerk Union AG
Publication of EP0042483A1 publication Critical patent/EP0042483A1/fr
Application granted granted Critical
Publication of EP0042483B1 publication Critical patent/EP0042483B1/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
    • G21F9/00—Treating radioactively contaminated material; Decontamination arrangements therefor
    • G21F9/28—Treating solids
    • G21F9/34—Disposal of solid waste

Definitions

  • the invention relates to a method for the final storage of elongated radioactive components of smaller cross section deformed into a coil.
  • the object of the invention is the elimination of instrumentation probes for a nuclear reactor.
  • instrumentation probes for a nuclear reactor.
  • Such probes can be several meters long, although their diameter is at most a few centimeters thick.
  • the tubes used to guide measuring lines in the reactor pressure vessels of pressure and boiling water reactors have a diameter of 6 m or more and are often smaller than 1 cm. If such probes have to be replaced, for example, due to a fault, sawing has so far been used for sawing to break them down into short sections, which can be carried out using normal means of transport, e.g. B. in the form of the known standard barrels with 2001 1 content could be removed.
  • disassembly is extremely difficult because of the strong activation of such probes.
  • the dismantled probes can only be transported to a processing facility in which the parts are in a form suitable for final storage, e.g. B. must be brought by embedding in concrete.
  • the invention achieves the final storage of the aforementioned probes in a simple manner and, above all, with less personnel in a radiation-endangered environment in that instrumentation probes for a reactor core are wound onto a bobbin and together with a remote-controlled winding machine during their removal from the reactor pressure vessel in the space below the vessel be accommodated with this in a shielding container and that the shielding container is then provided with a radiation-proof closure and transported to an intermediate and / or final storage facility.
  • the previous dismantling of the probes is completely eliminated.
  • the winding provided in the invention on a bobbin can be the only operation that is required for the final storage, because the shielding container itself can be designed so that it is suitable for final storage.
  • the bobbin may also be introduced together with other, preferably identical bobbins in larger containers, which are then intended for final storage and possibly after further conditioning, e.g. B. by pouring, with concrete.
  • the new method is preferably carried out in such a way that the coil former is inserted into the shielding container and wound there with the probe.
  • the bobbin can also be moved into the shielding container during winding. In this way, a certain guidance of the winding material on the bobbin is achieved.
  • the movement can be reciprocating, it being expediently ensured that the bobbin sits in the lowest position within the shielding container at the end of the winding process.
  • a drive motor and a transmission can be arranged on a base frame, which is coupled to the drive motor and actuates a shaft with a rotary movement and a longitudinal movement in the direction of the axis of rotation.
  • a pot-shaped shielding container is detachably fastened on the same base frame so that its opening faces the shaft. In this opening sits a coil former, which is connected to the shaft via a releasable coupling.
  • the shielding container consists of a suitable shielding material. In view of the mechanical loads, steel or cast iron are well suited for this. However, it can also be a metallically reinforced mineral material, such as concrete.
  • the wall thickness is measured with regard to the permissible surface dose rate. It will usually be between 200 and 400 mm.
  • the openings of the shielding container can be closed with screw-in shielding plugs.
  • the main plug provided for the insertion of the coil body should have a shaft which enables the coil body to be actuated when the plug is in place possible.
  • the coil former is expediently fastened in the shielding body with the flying bearing.
  • he can sit on a mandrel in the opening of the shielding container.
  • the bobbin as a whole or with a special coil part can be arranged so that it can be moved back and forth during the rotational movement of the shaft during the winding process. The force required for this longitudinal movement can be exerted by the material to be wound.
  • a sheathing tube can be assigned to the bobbin, which prevents the winding material from springing open and thus defines the outer diameter.
  • the cladding tube can be connected to the coil body in order to form a body that is easy to transport.
  • the shielding container has a bore which leads tangentially to the circumference of the coil former and which is inevitably closed by the coil former after the winding process has ended. In addition to this inevitable closure, other plugs can also be provided.
  • the shielding container can be assigned a guide tube with which it can be adjusted in relation to the respective place of use. This is particularly advantageous in the event that several spatial measuring lines not far from each other are to be transported away on a reactor pressure vessel.
  • the base frame provided for the new facility should have at least one radiation protection monitoring device. So that z. For example, inform the operating personnel necessary for »threading « about the risk of radiation. It can also be used to determine radiation levels that require decontamination.
  • a device for limiting the torque acting on the coil former can be assigned to the motor and / or the transmission. This is important in order to prevent excessive force flows on the component to be wound up or on the new device which can only be remedied in areas where there is a risk of radiation. For the same reason, a limit switch for a maximum longitudinal travel of the shaft should be assigned to the motor and / or the gear.
  • FIG. 1 shows a vertical section through the lower part of the reactor pressure vessel of a boiling water reactor with the control rod drives located there and the device placed underneath when a measuring probe is pulled.
  • 2 and 3 show this device in two mutually perpendicular vertical sections on a larger scale.
  • the bottom 3 of the reactor pressure vessel contains a plurality of connecting pieces 4 for control rod drives. Additional nozzles are provided for measuring probes 6, with which z. B. the neutron flow or the temperature or pressure of the cooling water can be determined.
  • the probes 6 are usually arranged in finger-thick metal tubes which are inserted into the reactor pressure vessel 1 by means of pressure-tight screw connections. Depending on the height at which the reactor pressure vessel is to be measured, its length is 4 to 10 m. This provides a component that can only be removed with difficulty in the event of a fault because it comes out of the reactor pressure vessel and is accordingly strongly activated. In addition, there is still a considerable radiation exposure below the control rod drives 4, so that work there is only possible with special protective measures.
  • a device designated as a whole by 10 is provided below the control rod drives, with which such probes 6 are pulled out of the reactor pressure vessel 1 and wound up in the process.
  • the device 10 comprises a base frame 11 on which a shielding container 12 z. B. is releasably attached at 13.
  • the shielding container 12 is a predominantly cylindrical pot with a wall thickness D of approximately 400 mm. Its opening 14, as shown in FIG. 3, sits centrally in the pot. It is closed with a stopper 15 except for an inner chamber in which a coil former 16 is supported on a mandrel 17 in a floating manner.
  • the bobbin 16 is in the operating position shown in Fig. 2 via a releasable coupling 18 which, for. B. is designed in the form of a toothed shaft, with a shaft 20 in connection, which is rotatably mounted in the plug 15, as the arrow 21 shows and also has a movement running in its longitudinal direction. This should be indicated by arrow 22.
  • a releasable coupling 18 which, for. B. is designed in the form of a toothed shaft, with a shaft 20 in connection, which is rotatably mounted in the plug 15, as the arrow 21 shows and also has a movement running in its longitudinal direction. This should be indicated by arrow 22.
  • the shaft 20 is assigned a drive shaft 23 which, via a torque limiter, not shown, for. B. is coupled in the form of a slip clutch 24 and a limit switch, not shown.
  • the drive shaft 23 is the output side of a gear 25 which is actuated by an electric motor 26.
  • FIG. 3 shows that in the pot-shaped shielding container 12 there is a bore 28 leading tangentially to the circumference of the opening 14, through which the probe 6 indicated in FIGS. 2 and 3 is only supplied to the coil former 16 by a dash-dotted line.
  • the insertion opening of a cladding tube 29, which limits the outer diameter of the winding material, is aligned with this bore.
  • Guide tubes 30, which are designed to be telescopic and are seated on an adjustable holder 31, are used to guide the probe 6 outside the shielding container 12.
  • the device 10 can be brought to a carriage 37 below the reactor pressure vessel 1 through a lock 35 with a transport device 36 designed as a suspension track.
  • This carriage is adjustable on a platform 38 acting as a turntable so that the guide tube 30 can move to the desired position of the probe 6 to be removed. The movement can already be done by remote control.
  • the device 10 After the threading and winding up of the probe, the device 10 can be transported so far without the use of personnel that it comes from the area 39 at risk of radiation into the area outside the shield 2. There, the shielding container 12 can be dismantled and, after possibly closing the openings there, in particular the bore 28, can be moved directly to a repository.
  • the bobbin 16 which is transported away practically radiation-free with the shielding container 12, is brought with the wound-up probe 6 and the cladding tube 29 into a system provided for handling radiation waste, where several bobbins are possibly placed in larger containers, which then be poured with concrete or another binding agent, so that a final storage product is created.

Claims (10)

1. Procédé pour le stockage final d'éléments radioactifs allongés de faible section transversale, moyennant une déformation les amenant sous la forme d'une bobine, caractérisé par le fait qu'on enroule, sur un corps de bobine, des sondes d'instrumentation pour un coeur de réacteur, pendant leur retrait hors du caisson sous pression de réacteur, dans l'espace situé audes- sous dudit caisson à l'aide d'une enrouleuse pouvant être télécommandée et qu'on place lesdites sondes ainsi que le corps de bobine dans un récipient de protection et qu'on munit ensuite ce récipient d'un dispositif de fermeture étanche au rayonnement et qu'on l'évacue jusqu'à un lieu de stockage intermédiaire et/ou final.
2. Procédé suivant la revendication 1, caractérisé par le fait qu'on place le corps de bobine dans le récipient de protection et que dans ce dernier on enroule la sonde sur ledit corps.
3. Procédé suivant la revendication 1, caractérisé par le fait qu'on introduit le corps de bobine dans le récipient de protection pendant l'enroulement de la sonde sur ledit corps.
4. Dispositif pour la mise en oeuvre du procédé suivant l'une des revendications 1 à 3, caractérisé par le fait que sur un cadre de base (11) se trouvent disposés un moteur d'entraînement (26) et une transmission (25) qui est accouplée au moteur d'entraînement (26) et actionne un arbre (20) selon un mouvement de rotation et un mouvement de déplacement longitudinal suivant la direction de l'axe de rotation, qu'un récipient de protection .(12) en forme de pot est fixé sur le cadre de base (11) d'une manière détachable en sorte que son ouverture (14) est tournée vers l'arbre (20), et que dans l'ouverture (14) prend appui un corps de bobine (16) qui est relié à l'arbre (20) par l'intermédiaire d'un accouplement détachable (18).
5. Dispositif suivant la revendication 4, caractérisé par le fait que le corps de bobine (16) prend appui sur une broche (17) dans l'ouverture (14) du récipient de protection (12).
6. Dispositif suivant la revendication 4 ou 5, caractérisé par le fait que le récipient de protection (12) possède un perçage (28) débouchant tangentiellement sur le pourtour du corps de bobine (16) et qui est obturé obligatoirement par le corps de bobine (16) à la fin de l'opérration d'enroulement.
7. Dispositif suivant la revendication 6, caractérisé par le fait qu'au corps de bobine (16) est associé un tube-enveloppe (29) qui possède un évidement associé au perçage (28).
8. Dispositif suivant l'une des revendications 4 à 7, caractérisé par le fait qu'au moteur (26) et/ou à la transmission (25) est associé un dispositif (24) servant à limiter le couple de rotation agissant sur le corps de bobine (16).
9. Dispositif suivant l'une des revendications 4 à 8, caractérisé par le fait que l'ouverture (14) du récipient de protection (12) doit être obturée avec un bouchon de protection (15) vissable et qu'un manchon d'entraînement du corps de bobine (16) doit être accouplé, dans le bouchon (15), à l'arbre de la transmission (25).
10. Dispositif suivant l'une des revendications 4 à 9, caractérisé par le fait qu'un élément de bobine dans le corps de bobine (16) peut être déplacé suivant un mouvement de va-et-vient lors du mouvement de rotation de l'arbre (20) pendant l'opération d'enroulement.
EP81103493A 1980-05-16 1981-05-07 Procédé et dispositif pour le stockage final d'éléments de construction de longue radioactivité Expired EP0042483B1 (fr)

Applications Claiming Priority (2)

Application Number Priority Date Filing Date Title
DE3018857A DE3018857C2 (de) 1980-05-16 1980-05-16 Verfahren und Einrichtung zur Einbringung von radioaktiven langgestreckten, metallischen Bauteilen in einen Abschirmbehälter
DE3018857 1980-05-16

Publications (2)

Publication Number Publication Date
EP0042483A1 EP0042483A1 (fr) 1981-12-30
EP0042483B1 true EP0042483B1 (fr) 1985-01-02

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EP81103493A Expired EP0042483B1 (fr) 1980-05-16 1981-05-07 Procédé et dispositif pour le stockage final d'éléments de construction de longue radioactivité

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EP (1) EP0042483B1 (fr)
JP (1) JPS578500A (fr)
DE (2) DE3018857C2 (fr)

Families Citing this family (4)

* Cited by examiner, † Cited by third party
Publication number Priority date Publication date Assignee Title
SE434586B (sv) * 1982-09-20 1984-07-30 Asea Atom Ab Sett for inneslutning av holjeror till forbrukade brensleboxar for brenslepatroner for kernkraftverk och minskning av volymen fore deponeringen jemte valsanordning for genomforande av settet
DD283091B5 (de) * 1989-05-17 1995-05-18 Asug Getriebewerk Dessau Gmbh Verfahren zur pruefung und korrektur der breitenlastverteilung bei zahnradpaarungen
DE4017987A1 (de) * 1990-06-05 1991-12-12 Battelle Institut E V Verfahren zur konditionierung verbrauchter steuerelemente und brennelementkaesten aus siedewasserreaktoren
DE19700651C1 (de) * 1997-01-10 1998-09-03 Siemens Ag Verdichtung zu entsorgender Steuer- und Absorberelemente aus Leichtwasser-Reaktoren

Family Cites Families (3)

* Cited by examiner, † Cited by third party
Publication number Priority date Publication date Assignee Title
FR2353117A1 (fr) * 1976-05-25 1977-12-23 Novatome Ind Procede de preparation au stockage de materiaux fractionnes solides
FR2388379A2 (fr) * 1977-04-18 1978-11-17 Novatome Ind Procede de preparation au stockage de materiaux fractionnes solides
SE413712B (sv) * 1977-05-10 1980-06-16 Asea Ab Sett att innesluta anvenda kernbrenslestavar i en skyddsbehallare for deponering

Also Published As

Publication number Publication date
DE3168013D1 (en) 1985-02-14
EP0042483A1 (fr) 1981-12-30
JPS578500A (en) 1982-01-16
JPS612920B2 (fr) 1986-01-28
DE3018857A1 (de) 1981-11-26
DE3018857C2 (de) 1984-10-25

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