EP0042483A1 - 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
EP0042483A1
EP0042483A1 EP81103493A EP81103493A EP0042483A1 EP 0042483 A1 EP0042483 A1 EP 0042483A1 EP 81103493 A EP81103493 A EP 81103493A EP 81103493 A EP81103493 A EP 81103493A EP 0042483 A1 EP0042483 A1 EP 0042483A1
Authority
EP
European Patent Office
Prior art keywords
shielding container
shaft
bobbin
coil
opening
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
Application number
EP81103493A
Other languages
German (de)
English (en)
Other versions
EP0042483B1 (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 small cross section, in particular of instrumentation probes for a reactor core.
  • Such components can have a length of several meters, although their diameter is at most a few centimeters thick.
  • the pipes used to guide measurement lines in the reactor pressure vessels of pressure and boiling water reactors are often less than 1 cm in diameter with a length of 6 m or more. If such components have to be replaced, for example due to a malfunction, sawing has so far been used to cut them down into short sections, which could be removed using normal means of transport, for example in the form of the well-known standard drums with a capacity of 200 liters however, extremely difficult due to the strong activation of such components.
  • the dismantled components can only be transported to a processing facility in which the parts have to be brought into a form suitable for final storage, for example by embedding in concrete.
  • the invention is based on the object of achieving the final storage of the aforementioned components in a simple manner and, above all, with fewer personnel in a radiation-endangered environment.
  • This object is achieved in that the components are wound onto a bobbin with a remote-controlled winding machine be housed together 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 disassembly of the components 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 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 component.
  • the bobbin can also be moved into the shielding container during winding. A certain guidance of the winding material on the bobbin is achieved in this way. In the case of multi-layer winding, the movement can be reciprocating, it being expedient to ensure 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 releasably attached 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.
  • the coil former is expediently fastened in the shielding body with the flying bearing. For this purpose, 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 move 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 tangential to the circumference of the bobbin bore which is inevitably closed by the bobbin after completion of the winding process. 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 a plurality of measuring lines that are not spatially far apart 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. This enables the operating personnel who are required, for example, to “thread in” information about the risk of radiation. It can also be used to determine radiation levels that require decontamination.
  • 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 pulling a measuring probe.
  • Figs. 2 and 3 show this Einrich - tung in two orthogonal vertical sections in a larger scale.
  • the reactor pressure vessel of a boiling water reactor for 1300 MW e for example, which is seated in a concrete shield 2, is designated by 1.
  • the bottom 3 of the reactor pressure vessel contains a plurality of connecting pieces 4 for control rod drives. Further nozzles are provided for measuring probes 6 with which, for example, the neutron flow or the temperature or the pressure of the cooling water are 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 is detachably fastened, for example at 13.
  • the shielding container 12 is a predominantly cylindrical pot with a wall thickness D of approximately 400 mm. His As shown in FIG. 3, opening 14 is centered 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 connected via a releasable coupling 18, which is designed, for example, in the form of a toothed shaft, to a shaft 20 which is rotatably mounted in the plug 15, as the arrow 21 shows and further comprising a verlau- f in its longitudinal direction of motion. This should be indicated by arrow 22.
  • the shaft 20 is assigned a drive shaft 23 which is coupled via a torque limiter, not shown, for example 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 bobbin 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 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.
  • the shielding container 12 can be dismantled and, after the openings thereon, in particular the bore 28, may have to be additionally closed, can be moved directly to a repository.
  • the bobbin 16 which is carried away with the shielding container 12 practically radiation-free, with the wound-up probe 6 and the cladding tube 29 is brought into a system intended 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.

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  • Engineering & Computer Science (AREA)
  • Environmental & Geological Engineering (AREA)
  • Physics & Mathematics (AREA)
  • General Engineering & Computer Science (AREA)
  • High Energy & Nuclear Physics (AREA)
  • Monitoring And Testing Of Nuclear Reactors (AREA)
  • Working Measures On Existing Buildindgs (AREA)
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
DE3018857 1980-05-16
DE3018857A DE3018857C2 (de) 1980-05-16 1980-05-16 Verfahren und Einrichtung zur Einbringung von radioaktiven langgestreckten, metallischen Bauteilen in einen Abschirmbehälter

Publications (2)

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

Family

ID=6102652

Family Applications (1)

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

Country Status (3)

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

Cited By (2)

* Cited by examiner, † Cited by third party
Publication number Priority date Publication date Assignee Title
GB2231443A (en) * 1989-05-17 1990-11-14 Freiberg Brennstoffinst Disposal method and apparatus
EP0853320A2 (fr) * 1997-01-10 1998-07-15 Siemens Aktiengesellschaft Compactage pour le stockage des éléments de commande et d'absortion des réacteurs à eau légère

Families Citing this family (2)

* 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
DE4017987A1 (de) * 1990-06-05 1991-12-12 Battelle Institut E V Verfahren zur konditionierung verbrauchter steuerelemente und brennelementkaesten aus siedewasserreaktoren

Citations (2)

* Cited by examiner, † Cited by third party
Publication number Priority date Publication date Assignee Title
DE2722472A1 (de) * 1976-05-25 1977-12-15 Novatome Ind Verfahren zur einlagerung von nuklearabfaellen, die als feststoffschuettung anfallen
DE2818781A1 (de) * 1977-05-10 1978-11-23 Asea Ab Verfahren zur umweltsicheren lagerung von verbrauchten radioaktiven kernbrennstaeben

Family Cites Families (1)

* Cited by examiner, † Cited by third party
Publication number Priority date Publication date Assignee Title
FR2388379A2 (fr) * 1977-04-18 1978-11-17 Novatome Ind Procede de preparation au stockage de materiaux fractionnes solides

Patent Citations (4)

* Cited by examiner, † Cited by third party
Publication number Priority date Publication date Assignee Title
DE2722472A1 (de) * 1976-05-25 1977-12-15 Novatome Ind Verfahren zur einlagerung von nuklearabfaellen, die als feststoffschuettung anfallen
FR2353117A1 (fr) * 1976-05-25 1977-12-23 Novatome Ind Procede de preparation au stockage de materiaux fractionnes solides
DE2818781A1 (de) * 1977-05-10 1978-11-23 Asea Ab Verfahren zur umweltsicheren lagerung von verbrauchten radioaktiven kernbrennstaeben
FR2390811A1 (fr) * 1977-05-10 1978-12-08 Asea Ab Procede pour mettre des barreaux de combustible nucleaire epuise dans un conteneur protecteur

Non-Patent Citations (1)

* Cited by examiner, † Cited by third party
Title
Elektrotechnik, Jahrgang 60, Nr. 4, Februar 1978, seite 24 "Fortschritte bei der Kapselung von Kernbrennstoffabfall" * figuren 1,2 * *

Cited By (3)

* Cited by examiner, † Cited by third party
Publication number Priority date Publication date Assignee Title
GB2231443A (en) * 1989-05-17 1990-11-14 Freiberg Brennstoffinst Disposal method and apparatus
EP0853320A2 (fr) * 1997-01-10 1998-07-15 Siemens Aktiengesellschaft Compactage pour le stockage des éléments de commande et d'absortion des réacteurs à eau légère
EP0853320A3 (fr) * 1997-01-10 1998-10-14 Siemens Aktiengesellschaft Compactage pour le stockage des éléments de commande et d'absortion des réacteurs à eau légère

Also Published As

Publication number Publication date
DE3018857A1 (de) 1981-11-26
DE3168013D1 (en) 1985-02-14
JPS612920B2 (fr) 1986-01-28
DE3018857C2 (de) 1984-10-25
EP0042483B1 (fr) 1985-01-02
JPS578500A (en) 1982-01-16

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