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WO1997039454A1 - Procede pour introduire un element combustible de reacteur nucleaire irradie individuel dans une boite-bidon - Google Patents

Procede pour introduire un element combustible de reacteur nucleaire irradie individuel dans une boite-bidon Download PDF

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Publication number
WO1997039454A1
WO1997039454A1 PCT/EP1997/001810 EP9701810W WO9739454A1 WO 1997039454 A1 WO1997039454 A1 WO 1997039454A1 EP 9701810 W EP9701810 W EP 9701810W WO 9739454 A1 WO9739454 A1 WO 9739454A1
Authority
WO
WIPO (PCT)
Prior art keywords
canister
water
container
nuclear reactor
fuel element
Prior art date
Application number
PCT/EP1997/001810
Other languages
German (de)
English (en)
Inventor
Volker Dannert
Wolfgang Hummel
Martin Peehs
Original Assignee
Siemens Aktiengesellschaft
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 Siemens Aktiengesellschaft filed Critical Siemens Aktiengesellschaft
Priority to JP9536728A priority Critical patent/JP2000508426A/ja
Priority to EP97919335A priority patent/EP0892977A1/fr
Publication of WO1997039454A1 publication Critical patent/WO1997039454A1/fr

Links

Classifications

    • G—PHYSICS
    • G21—NUCLEAR PHYSICS; NUCLEAR ENGINEERING
    • G21C—NUCLEAR REACTORS
    • G21C19/00—Arrangements for treating, for handling, or for facilitating the handling of, fuel or other materials which are used within the reactor, e.g. within its pressure vessel
    • G21C19/32—Apparatus for removing radioactive objects or materials from the reactor discharge area, e.g. to a storage place; Apparatus for handling radioactive objects or materials within a storage place or removing them therefrom
    • Y—GENERAL TAGGING OF NEW TECHNOLOGICAL DEVELOPMENTS; GENERAL TAGGING OF CROSS-SECTIONAL TECHNOLOGIES SPANNING OVER SEVERAL SECTIONS OF THE IPC; TECHNICAL SUBJECTS COVERED BY FORMER USPC CROSS-REFERENCE ART COLLECTIONS [XRACs] AND DIGESTS
    • Y02—TECHNOLOGIES OR APPLICATIONS FOR MITIGATION OR ADAPTATION AGAINST CLIMATE CHANGE
    • Y02E—REDUCTION OF GREENHOUSE GAS [GHG] EMISSIONS, RELATED TO ENERGY GENERATION, TRANSMISSION OR DISTRIBUTION
    • Y02E30/00—Energy generation of nuclear origin
    • Y02E30/30—Nuclear fission reactors

Definitions

  • the invention relates to a method for inserting an individual irradiated nuclear reactor fuel element under water into a canister set up under water, which is then sealed under water with a canister lid and welded gas-tight and then inserted under water into a transport container set up under water, which thereupon, also under water, closed with a container lid suitable for shielding from rays and then lifted out of the water and placed outside the water.
  • the method according to the invention can be carried out in a nuclear power plant in a storage pool for spent nuclear reactor fuel elements. It is sufficient to use the canister containing the nuclear reactor fuel element and closed with a lid and welded in a gas-tight manner with the lifting tool, which is designed to lift and transport a single nuclear reactor fuel element within the reactor building.
  • the transport container After the insertion of a corresponding number under water, each containing a single irradiated nuclear reactor fuel element and sealing with a container cover suitable for shielding against radiation, the transport container can be lifted out of the water and set down outside the water. It is advantageous if the water is removed from the transport container after it has been closed with the container lid before the transport container is lifted out of the water. The water can also be removed from the transport container after it has been placed outside the water. Finally, the transport container can be closed with an additional lid and is still ready for decontamination for transport to an intermediate storage facility.
  • connection piece on the canister After it has been welded and then inert gas is filled into the canister.
  • the connection opening is then closed gas-tight. This prevents corrosion within the canister, particularly on the irradiated nuclear reactor fuel element is largely prevented in the canister.
  • the inert gas also ensures good dissipation of the post-decay heat from the emitted nuclear reactor fuel element to the wall of the canister.
  • a good effectiveness, in particular of a welding device, with which a canister lid, with which the canister is closed and welded in a gas-tight manner, is ensured if the canister is placed in a container located under water.
  • the nuclear reactor fuel element is used in this container after the water has been removed from the container and from the canister.
  • the canister is then sealed gas-tight to the canister lid and welded.
  • the container is then flooded to remove the canister.
  • FIG. 1 shows a longitudinal section of a storage pool for spent nuclear reactor fuel elements in a nuclear power plant.
  • FIG. 2 shows in longitudinal section a canister with an irradiated nuclear reactor fuel element from the storage pool according to FIG. 1.
  • a canister 2 can be seen in position 1, which is closed off with a bottom at the lower end and forms an opening at the upper end.
  • This canister 2 is under water.
  • a burned-off and irradiated nuclear reactor fuel element 3 is inserted into it, which, with its fuel element head 3a, hangs on a lifting tool 4 and already engages in the canister 2 with its fuel element foot 3b.
  • a can 2 can be seen in which the nuclear reactor fuel element 3 has already been inserted.
  • the opening at the upper end of the canister 2 is closed with a canister lid 5 which is welded gas-tight to the canister wall of the canister 2 just under water with the aid of a welding device 6.
  • FIG. 2 shows canister 2 from position II in FIG. 1.
  • the irradiated nuclear reactor fuel element 3 is located as the only nuclear reactor fuel element.
  • This nuclear reactor fuel element 3 has the fuel element head 3a and the fuel element foot 3b, both of which have the same square cross section, furthermore it has control rod guide tubes 3c which are screwed to the fuel element head 3a at one end and to the fuel element foot 3b at the other end.
  • grid-shaped spacers 3d can be seen with grid meshes, through which a control rod guide tube 3c or a fuel rod 3e containing nuclear fuel is guided.
  • the fuel rods 3e are held on the lattice meshes of the lattice-shaped spacers 3b in a force-locking manner, ie they are held in the lattice mesh by springs which are formed on a wall of the lattice mesh and the m press the fuel rod located on this mesh against rigid knobs on other walls of the mesh.
  • the canister cover 5 with which the opening at the upper end of the canister 2 according to FIG. 2 is closed and which is welded gas-tight to the inside of the canister wall of the canister 2, has a connection piece 5a in the center, which extends through a bushing the lid 5 is located.
  • a connection piece 5a Connected to this socket 5a on the outside is a hose 5b, through which the water is sucked out of the canister under water in the storage tank according to FIG. 1 and through which inert gas, for example nitrogen or, is removed after the water has been removed a noble gas such as argon or helium is filled.
  • the connecting piece 5a - still under water - is squeezed together with a squeezing tool in the direction of the two arrows 6b and welded gas-tight with the welding device 6 - likewise under water.
  • the canister 2 is lifted from the position II in FIG. 1 with the aid of the lifting tool 4 in accordance with FIG. 2 and inserted into a transport container 7 which is in position 3 in FIG. 1 under water.
  • a transport container 7 which is filled with canisters 2, of which each canister 2 contains only a single spent and therefore irradiated nuclear reactor fuel element. These canisters 2 stand upright and side by side with a parallel longitudinal axis.
  • the transport container 7 is already closed with a container cover 8, which shields the radioactive radiation emanating from the nuclear reactor fuel elements 2.
  • the container lid 8 is loosely inserted into the opening at the upper end of the container 7, rests on a shoulder on the inside of the wall of the container 7 and is sealed by a sealing body 9 inserted in the shoulder.
  • a tube 10 with a valve on the outside of this container cover 8 grips through the container cover 8.
  • the water can be sucked out of the transport container 7 through this tube 10 and the transport container 7 can be filled with inert gas such as nitrogen or a noble gas such as argon or helium.
  • the valve on the tube 10 on the outside of the container cover 8 is then closed.
  • the container 7 can then be lifted out of the water of the storage basin according to FIG. 1 with a crane and placed at the edge of the basin. 1 shows in the position V em such a container 7 placed on the edge of the pool, which after being deposited on the edge of the pool was still closed with an additional cover 11 which covers the cover 8 of the container.
  • the container 7 can also be lifted out of the storage pool with the water in it and placed at the pool edge. The water is then sucked through the pipe 10 from the container 7 located in position V. Then this container 7 in position V is filled through the pipe 10 with inert gas such as nitrogen or the noble gas. Then the valve 10 on the outside of the container cover 8 is closed and the container 7 in position V is closed with the additional cover 11.
  • inert gas such as nitrogen or the noble gas
  • the container 7 located in position V can be decontaminated and transported to an intermediate store. After a sufficiently long decay time, the container 7 can then be transported to a repository, where the additional cover 11 and the container cover 8 are removed and the canisters in the container 7 with the spent nuclear reactor fuel elements 3 are brought to a geological repository, for example, without that they were opened. Since these canisters 2 contain only a single nuclear reactor fuel element, they are easy to handle in this procedure.
  • FIGS. 3 to 6 show in longitudinal section a working container 20 which is located under water in the storage tank according to FIG. 1 and in which the method steps are carried out which are carried out in positions I and II in the storage tank according to FIG.
  • the welding device 6, which hangs on a hanger 6a, is located in the working container 20 according to FIGS. 3 to 6. Furthermore, the working container 20 has a passage 21 on its container ceiling, which is gas-tight with a cover 22. is closable. Finally, a lifting tool 25 and a suction pipe 26 are also provided in the working container 20, which, like the hanger 6a, are attached to the inside of the ceiling of the working container 20.
  • the lid 22 is open.
  • the spent nuclear reactor fuel element 3 was placed in the working container 20 on the container bottom with the lifting tool 4 and the position shown in FIG. 3 was set aside with the lifting tool 25.
  • the canister 2 which was open at the upper end, was placed in the working container 20 on the container bottom under the passage 21.
  • the lid 22 is closed and the water is withdrawn from the working container 20 through a non-drained drain opening.
  • the water is drawn off from the canister 2 with the aid of the suction pipe 26.
  • the working container 20 is filled with dry inert gas through a supply opening (not shown), so that both the switched off nuclear reactor fuel element and the canister 2 open at the top can dry out.
  • the nuclear reactor fuel element 3 m placed in the working container 20 m FIG. 3 m and the canister 2 likewise placed in this working container 20 are inserted, so that the state shown in FIG. 4 results in the working container 20.
  • a canister lid (not shown in FIG. 4) is inserted into the opening at the upper end of the canister 2 with the aid of the lifting device 25.
  • This canister lid 5 inserted at the upper end of the canister 2 can be seen in FIG. It is welded gas-tight to the inside of the canister wall of the canister 2 with the aid of the welding device 6.
  • the working container 20 is then flooded again with water through a flood opening shown, so that the cover 22 can finally be opened again.
  • the gas-tightly closed canister 2 can be lifted out of the working container 20 with the lifting tool 4 and the transport container 7, which is in position III in FIG. 1, can be inserted under water.

Landscapes

  • Physics & Mathematics (AREA)
  • Engineering & Computer Science (AREA)
  • Plasma & Fusion (AREA)
  • General Engineering & Computer Science (AREA)
  • High Energy & Nuclear Physics (AREA)
  • Butt Welding And Welding Of Specific Article (AREA)
  • Monitoring And Testing Of Nuclear Reactors (AREA)

Abstract

Un élément combustible de réacteur nucléaire (3) irradié individuel est introduit sous l'eau dans une boîte-bidon (2) immergée. Cette boîte-bidon (2) est fermée sous l'eau avec un couvercle (5) et est soudée de manière étanche au gaz. Elle est ensuite introduite dans un conteneur de transport (7) immergé, lui aussi fermé avec un couvercle (8) approprié pour protéger des radiations, avant d'être sorti de l'eau et déposé.
PCT/EP1997/001810 1996-04-12 1997-04-11 Procede pour introduire un element combustible de reacteur nucleaire irradie individuel dans une boite-bidon WO1997039454A1 (fr)

Priority Applications (2)

Application Number Priority Date Filing Date Title
JP9536728A JP2000508426A (ja) 1996-04-12 1997-04-11 個々の照射済原子炉燃料要素をキャニスタの中に入れる方法
EP97919335A EP0892977A1 (fr) 1996-04-12 1997-04-11 Procede pour introduire un element combustible de reacteur nucleaire irradie individuel dans une boite-bidon

Applications Claiming Priority (2)

Application Number Priority Date Filing Date Title
DE19614553 1996-04-12
DE19614553.8 1996-04-12

Publications (1)

Publication Number Publication Date
WO1997039454A1 true WO1997039454A1 (fr) 1997-10-23

Family

ID=7791130

Family Applications (1)

Application Number Title Priority Date Filing Date
PCT/EP1997/001810 WO1997039454A1 (fr) 1996-04-12 1997-04-11 Procede pour introduire un element combustible de reacteur nucleaire irradie individuel dans une boite-bidon

Country Status (3)

Country Link
EP (1) EP0892977A1 (fr)
JP (1) JP2000508426A (fr)
WO (1) WO1997039454A1 (fr)

Cited By (5)

* Cited by examiner, † Cited by third party
Publication number Priority date Publication date Assignee Title
FR2806828A1 (fr) * 2000-03-27 2001-09-28 Commissariat Energie Atomique Procede et dispositif de fermeture sous eau d'un etui de combustible irradie
EP1351257A1 (fr) * 2002-03-18 2003-10-08 Holtec International, Inc. Procédé et dispositif visant à assurer une protection renforcée contre les rayonnements pendant des opérations de transfert entre conteneurs
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
EP2503557A3 (fr) * 2011-03-25 2013-10-09 Rolls-Royce plc Centrale nucléaire
US9208914B2 (en) 2009-11-05 2015-12-08 Holtec International System, method and apparatus for providing additional radiation shielding to high level radioactive materials

Families Citing this family (2)

* Cited by examiner, † Cited by third party
Publication number Priority date Publication date Assignee Title
JP4575204B2 (ja) * 2005-03-28 2010-11-04 日立Ｇｅニュークリア・エナジー株式会社 使用済燃料の処理方法
CN108689299B (zh) * 2018-05-22 2019-11-01 广东核电合营有限公司 百万千瓦级乏燃料水池扩容用旧格架拆除翻转工艺

Citations (5)

* Cited by examiner, † Cited by third party
Publication number Priority date Publication date Assignee Title
FR2530065A1 (fr) * 1982-07-07 1984-01-13 Doryokuro Kakunenryo Procede de manutention de chateau et double recipient pour sa mise en oeuvre
FR2530366A1 (fr) * 1982-07-19 1984-01-20 Kraftwerk Union Ag Procede pour le confinement etanche au gaz d'elements radioactifs et installation pour la mise en oeuvre dudit procede
JPH06324199A (ja) * 1993-05-14 1994-11-25 Ishikawajima Harima Heavy Ind Co Ltd 使用済核燃料の封入方法及び封入設備
JPH07218686A (ja) * 1994-02-04 1995-08-18 Ishikawajima Harima Heavy Ind Co Ltd 使用済燃料体のキャニスタへの装荷方法および装置
JPH0829584A (ja) * 1994-07-15 1996-02-02 Ishikawajima Harima Heavy Ind Co Ltd 放射能汚染物の収納移送方法及び収納移送設備

Patent Citations (5)

* Cited by examiner, † Cited by third party
Publication number Priority date Publication date Assignee Title
FR2530065A1 (fr) * 1982-07-07 1984-01-13 Doryokuro Kakunenryo Procede de manutention de chateau et double recipient pour sa mise en oeuvre
FR2530366A1 (fr) * 1982-07-19 1984-01-20 Kraftwerk Union Ag Procede pour le confinement etanche au gaz d'elements radioactifs et installation pour la mise en oeuvre dudit procede
JPH06324199A (ja) * 1993-05-14 1994-11-25 Ishikawajima Harima Heavy Ind Co Ltd 使用済核燃料の封入方法及び封入設備
JPH07218686A (ja) * 1994-02-04 1995-08-18 Ishikawajima Harima Heavy Ind Co Ltd 使用済燃料体のキャニスタへの装荷方法および装置
JPH0829584A (ja) * 1994-07-15 1996-02-02 Ishikawajima Harima Heavy Ind Co Ltd 放射能汚染物の収納移送方法及び収納移送設備

Non-Patent Citations (3)

* Cited by examiner, † Cited by third party
Title
PATENT ABSTRACTS OF JAPAN vol. 095, no. 002 31 March 1995 (1995-03-31) *
PATENT ABSTRACTS OF JAPAN vol. 095, no. 011 26 December 1995 (1995-12-26) *
PATENT ABSTRACTS OF JAPAN vol. 096, no. 006 28 June 1996 (1996-06-28) *

Cited By (7)

* Cited by examiner, † Cited by third party
Publication number Priority date Publication date Assignee Title
FR2806828A1 (fr) * 2000-03-27 2001-09-28 Commissariat Energie Atomique Procede et dispositif de fermeture sous eau d'un etui de combustible irradie
EP1351257A1 (fr) * 2002-03-18 2003-10-08 Holtec International, Inc. Procédé et dispositif visant à assurer une protection renforcée contre les rayonnements pendant des opérations de transfert entre conteneurs
US7330525B2 (en) 2002-03-18 2008-02-12 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
US8277746B2 (en) 2006-07-10 2012-10-02 Holtec International, Inc. Apparatus, system and method for facilitating transfer of high level radioactive waste to and/or from a pool
US9208914B2 (en) 2009-11-05 2015-12-08 Holtec International System, method and apparatus for providing additional radiation shielding to high level radioactive materials
EP2503557A3 (fr) * 2011-03-25 2013-10-09 Rolls-Royce plc Centrale nucléaire

Also Published As

Publication number Publication date
JP2000508426A (ja) 2000-07-04
EP0892977A1 (fr) 1999-01-27

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