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EP0061067A1 - Procédé pour enfermer dans un récipient en cuivre les combustible usées d'un réacteur nucléaire - Google Patents

Procédé pour enfermer dans un récipient en cuivre les combustible usées d'un réacteur nucléaire Download PDF

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Publication number
EP0061067A1
EP0061067A1 EP82101891A EP82101891A EP0061067A1 EP 0061067 A1 EP0061067 A1 EP 0061067A1 EP 82101891 A EP82101891 A EP 82101891A EP 82101891 A EP82101891 A EP 82101891A EP 0061067 A1 EP0061067 A1 EP 0061067A1
Authority
EP
European Patent Office
Prior art keywords
container
lid
copper
tight
fuel rods
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
EP82101891A
Other languages
German (de)
English (en)
Other versions
EP0061067B1 (fr
Inventor
Hans Larker
Ragnar Tegman
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.)
ABB Norden Holding AB
Original Assignee
ASEA AB
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 ASEA AB filed Critical ASEA AB
Publication of EP0061067A1 publication Critical patent/EP0061067A1/fr
Application granted granted Critical
Publication of EP0061067B1 publication Critical patent/EP0061067B1/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
    • G21F5/005—Containers for solid radioactive wastes, e.g. for ultimate disposal
    • 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
    • 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
    • G21F9/36—Disposal of solid waste by packaging; by baling

Definitions

  • the invention relates to a method for enclosing spent fuel rods of a nuclear reactor in a copper container according to the preamble of claim 1.
  • spent fuel rods from a nuclear reactor are directly, i.e. without refurbishment, enclosed in sealed containers made of corrosion-resistant material.
  • spent fuel rods are placed in a copper container and embedded in lead in the container by supplying molten lead to the container, which then solidifies in the container.
  • the container is then provided with a copper lid which is welded to the container to form a tight seam.
  • the invention has for its object to develop a method of the type mentioned, in which the body to be finally stored is more resistant to corrosion attacks and more dense to the outside.
  • the invention is based on the finding that considerable advantages are achieved when copper powder is used instead of lead as embedding material for the spent fuel rods and when the container and the lid are closed by isostatic pressing.
  • a higher resistance to corrosion attacks is achieved in that the solid copper body formed from the copper powder, the container and the lid is more resistant to corrosion than a copper container with a lead body arranged therein. This is due on the one hand to the fact that copper is more resistant per se than lead and on the other hand to the fact that the protective layers consist of a uniform material.
  • Another advantage is that the inside of the container can be made free of cavitation, which is hardly possible when pouring lead into the container and welding a lid.
  • Another advantage is that the seam between the container and the lid in the method according to the invention is completely tight and completely reliable.
  • the materials of the container and the lid merge into one another without a joint or a transition point with a different material composition being present between the container and the lid.
  • the welding of copper parts with a large wall thickness is associated with great difficulties and results in a seam which has a different structure than the adjacent material. The seam can therefore become a weakened area in the closed container.
  • the gas-tight capsule can remain on the finished pressed body if it is for final storage is deposited.
  • the capsule can be made of sheet metal of the same quality as the container, ie of copper. This considerably reduces the probability that a coherent material defect or a defect in the copper material can occur.
  • the outer capsule can also be made from another material that provides additional corrosion protection for copper, such as stainless steel or titanium.
  • the container, the lid and the copper powder are preferably made from a copper of high purity, low oxygen content, at least 99.95% Cu (including small amounts of Ag), a so-called OFHC type (Oxygen Free High Conductivity). Such quality is believed to give the finished product good corrosion resistance.
  • high-purity copper can be used, which has been deoxidized with small amounts of phosphorus (max. 0.015% P).
  • the particles of the copper powder are preferably spherical or at least predominantly spherical. Particles with such a shape have good fluidity and thus result in a high degree of filling. The degree of filling can be improved by using spherical powder with at least two different grain sizes.
  • a suitable grain size for one of the two fractions is 0.5-1.5 mm and for the other fraction 0.1-0.2 mm.
  • the latter fraction can alternatively be a graded fraction with a maximum grain size of 0.2 mm.
  • the fact that the container and / or the fuel assemblies is exposed to slight impacts or vibrations when filled can further improve the degree of filling of the copper powder.
  • a vibrating ramming device can be temporarily placed on or in the filled copper powder for the same purpose.
  • the isostatic pressing to form the coherent, tight unit from the container, lid and powder takes place preferably at a pressure of at least 10 MPa and at a temperature of 600-800 ° C, or even better at a temperature of 500-800 ° C.
  • the spacer elements are spacers, usually made of stainless steel, in which the fuel rods are combined to form fuel bundles, are arranged in the nuclear reactor during operation. After the fuel rods in the reactor have been used up, the fuel bundles can be placed in the copper container without any assembly work and can be treated for containment and final storage in accordance with the present invention.
  • the spacer elements consist of copper. This embodiment is particularly suitable when the fuel rods are dismantled, i.e. are not arranged in the form of bundles in spacers. Spacers made of copper with the poured-in copper powder surrounding them result in a homogeneous unit without any transition points with a different structure.
  • the copper components are one by isostatic pressing at a temperature lower than that used in the final pressing Subjected to creep.
  • the copper components are either arranged in the sealed, gas-tight capsule that is used in the final pressing, or they are arranged — if the capsule is not used — in such a way that the lid is connected to the container in a gas-tight manner is.
  • a pressure of at least 10 MPa and a temperature of 300-500 ° C is preferably used.
  • the copper parts By isostatically pressing the copper parts in this way at a temperature lower than the temperature used in the final assembly of the parts, one obtains an effective support pressure on the fuel rods of the fuel rods during further heating.
  • This can eliminate or at least substantially reduce the risk that the gas in the fuel pipes, when heated further to the temperature required for the formation of a coherent unit from the copper constituents powder, container and lid, causes such a pressure that in an expansion fracture occurs in the fuel pipes.
  • the fuel pipes contain gases, including helium and fission gases, which can cause a pressure of 50 - 80 bar in the fuel rods even at room temperature.
  • FIG. 1 a large number of spent fuel rods 11 of a nuclear reactor are arranged in a copper container 10.
  • the fuel rods which consist of circular tubes with uranium dioxide tablets stacked therein, remain in the spacers 12 which hold the fuel rods of each fuel bundle together in the nuclear reactor.
  • FIGS. 1 and 2 show four fuel bundles 13, 14, 15 and 16.
  • the fuel bundles may be placed on supports, not shown, on the bottom of the container or on a bed of copper powder.
  • the container is then whole with vibration with a powder mixture 17 of 70 parts by weight of a powder with spherical particles with a diameter of 0.5-1.5 mm and 30 parts by weight of a powder with spherical particles with a diameter of 0.1-0 , 2 mm filled.
  • a copper lid 18 is then placed on the container.
  • Containers, lids and powder consist of the copper quality mentioned at the beginning, which contains 99.95% Cu (including small amounts of Ag).
  • the part 19 of the lid, which rests on the container, is designed step-like.
  • the lid has a central, lower part 20 which projects into the container.
  • the surfaces 10a and 18a of the container 10 and the lid 18 which abut one another are textured, as can be seen in FIG. The surfaces are cleaned well before the lid is placed on the container and freed of oxide with acid.
  • the container with lid and contents is placed in a capsule 21 made of copper sheet or sheet steel, the lid 22 made of copper sheet or sheet steel is welded tight to form a gas-tight seam 23.
  • the lid is provided with a pipe socket 24 made of copper or steel, which can be connected to a vacuum pump for the purpose of evacuating the capsule with its contents. After the evacuation, the capsule is closed by welding the pipe socket above the upper surface of the lid.
  • the capsule with its contents is hot isostatically pressed in two steps using a gas, for example argon, as pressure medium in an oven for isostatic pressing of the type described in DE-OS 27 47 951.
  • a gas for example argon
  • the capsule is exposed to a pressure of 80 MPa and a temperature of 450-500 ° C for 2-10 hours.
  • the copper of the container, the lid and the powder experience one Creep, which has the consequence that the filling from the copper powder gives the fuel rods an effective support pressure, which prevents expansion fracture in the Zircaloy tubes, which could occur because the pressure of the gas in these tubes increases with further heating.
  • this treatment does not result in the powder granules, the container and the lid forming a fully bonded unit.
  • a mixture 17 which consists of 55 parts by weight of a powder with spherical particles with a diameter of 0.8-1.0 mm and from 45 parts by weight of a powder with spherical particles with a diameter of 0.2 mm and below consists. This gives a bulk density of 81% of the theoretical density.
  • the capsule 21 and its contents have been evacuated, the capsule is heated to 350 ° C., whereupon it is filled with hydrogen gas at a pressure of 0.1 MPa. After maintaining this temperature for half an hour, the capsule is evacuated and refilled with hydrogen gas. This treatment with hydrogen gas at 350 ° C. is repeated several times, for example seven times, expediently with a successively extended treatment time, for example up to 10 hours.
  • the hydrogen gas treatment causes a reduction in copper oxides that may be present.
  • the The capsule is evacuated and, as in the case described above, closed.
  • the isostatic pressing is carried out during the first step at 400-450 0 C and during the second step at 525 0 C. This alternative embodiment is otherwise carried out under the same conditions as in the previously described case.
  • the container 10 and the lid 18 are each provided with a flange 25 and 26, respectively.
  • the flanges 25 and 26 are joined by welding or cold pressing to form a gas-tight seam 27.
  • the lid is provided with a pipe socket 28 made of copper, which is closed with a gas-tight lid after the evacuation of the container. After closing, the closed container is isostatically pressed in two steps in the manner described for the closed capsule according to FIG. 1.

Landscapes

  • Engineering & Computer Science (AREA)
  • Physics & Mathematics (AREA)
  • General Engineering & Computer Science (AREA)
  • High Energy & Nuclear Physics (AREA)
  • Environmental & Geological Engineering (AREA)
  • Pressure Welding/Diffusion-Bonding (AREA)
  • Press Drives And Press Lines (AREA)
  • Filling Or Discharging Of Gas Storage Vessels (AREA)
  • Powder Metallurgy (AREA)
EP82101891A 1981-03-20 1982-03-10 Procédé pour enfermer dans un récipient en cuivre les combustible usées d'un réacteur nucléaire Expired EP0061067B1 (fr)

Applications Claiming Priority (2)

Application Number Priority Date Filing Date Title
SE8101778 1981-03-20
SE8101778A SE425707B (sv) 1981-03-20 1981-03-20 Sett att innesluta utbrenda kernbrenslestavar i en behallare av koppar

Publications (2)

Publication Number Publication Date
EP0061067A1 true EP0061067A1 (fr) 1982-09-29
EP0061067B1 EP0061067B1 (fr) 1985-11-13

Family

ID=20343383

Family Applications (1)

Application Number Title Priority Date Filing Date
EP82101891A Expired EP0061067B1 (fr) 1981-03-20 1982-03-10 Procédé pour enfermer dans un récipient en cuivre les combustible usées d'un réacteur nucléaire

Country Status (8)

Country Link
US (1) US4491540A (fr)
EP (1) EP0061067B1 (fr)
JP (1) JPS57168200A (fr)
CA (1) CA1190332A (fr)
DE (1) DE3267356D1 (fr)
ES (1) ES8402111A1 (fr)
FI (1) FI72008C (fr)
SE (1) SE425707B (fr)

Cited By (8)

* Cited by examiner, † Cited by third party
Publication number Priority date Publication date Assignee Title
EP0077955A2 (fr) * 1981-10-28 1983-05-04 Deutsche Gesellschaft für Wiederaufarbeitung von Kernbrennstoffen mbH Container de combustibles pour le transport et/ou l'emmagasinage de combustibles nucléaires
EP0084840A1 (fr) * 1982-01-22 1983-08-03 Deutsche Gesellschaft für Wiederaufarbeitung von Kernbrennstoffen mbH Procédé pour fermer un récipient contenant des substances radio-actives
EP0104398A1 (fr) * 1982-08-26 1984-04-04 Deutsche Gesellschaft für Wiederaufarbeitung von Kernbrennstoffen mbH Conteneur pour le stockage à sec d'éléments combustibles nucléaires épuisés
EP0141967A1 (fr) * 1983-09-24 1985-05-22 STEAG Kernenergie GmbH Procédé de fermeture d'un récipient pour le stockage de produits radioactifs
GB2151068A (en) * 1983-12-09 1985-07-10 Kernforschungsanlage Juelich Process for storing fuel elements
DE3720731A1 (de) * 1986-06-25 1988-01-07 Atomic Energy Of Australia Einkapselung von abfallstoffen
DE102004059216B3 (de) * 2004-12-09 2006-06-01 Forschungszentrum Karlsruhe Gmbh Verfahren zur Einlagerung radioaktiver Reststoffe, Behälter dafür und seine Verwendung
EP2160736A4 (fr) * 2007-05-25 2016-03-30 Swedish Metallurg And Mining Ab Réceptacle final de combustible nucléaire épuisé

Families Citing this family (18)

* Cited by examiner, † Cited by third party
Publication number Priority date Publication date Assignee Title
DE8236359U1 (de) * 1982-12-24 1983-06-30 Deutsche Gesellschaft für Wiederaufarbeitung von Kernbrennstoffen mbH, 3000 Hannover Lagerbehaelter fuer radioaktives material
US4738799A (en) * 1983-10-28 1988-04-19 Westinghouse Electric Corp. Permanent disposal of radioactive particulate waste
US4623510A (en) * 1983-10-28 1986-11-18 Westinghouse Electric Corp. Permanent disposal of radioactive particulate waste in cartridge containing ferromagnetic material
DE3503641A1 (de) * 1984-07-24 1986-02-06 Nationale Genossenschaft für die Lagerung radioaktiver Abfälle - NAGRA, Baden Verfahren zum schliessen eines behaelters zur aufnahme von radioaktivem material und behaelter zur durchfuehrung des verfahrens
FR2648611B2 (fr) * 1988-12-12 1994-08-19 Cogema Conteneur de stockage pour dechets radioactifs
US4963317A (en) * 1989-09-13 1990-10-16 The United States Of America As Represented By The United States Department Of Energy High loading uranium fuel plate
JPH087279B2 (ja) * 1989-09-28 1996-01-29 動力灯・核燃料開発事業団 放射性廃棄物の処理用容器の真空脱気方法
JP2547453B2 (ja) * 1989-09-28 1996-10-23 動力灯・核燃料開発事業団 放射性金属廃棄物の減容処理方法
US5401319A (en) * 1992-08-27 1995-03-28 Applied Materials, Inc. Lid and door for a vacuum chamber and pretreatment therefor
US5488644A (en) * 1994-07-13 1996-01-30 General Electric Company Spring assemblies for adjoining nuclear fuel rod containing ferrules and a spacer formed of the spring assemblies and ferrules
US5519747A (en) * 1994-10-04 1996-05-21 General Electric Company Apparatus and methods for fabricating spacers for a nuclear fuel rod bundle
US5546437A (en) * 1995-01-11 1996-08-13 General Electric Company Spacer for nuclear fuel rods
US5566217A (en) * 1995-01-30 1996-10-15 General Electric Company Reduced height spacer for nuclear fuel rods
US5675621A (en) * 1995-08-17 1997-10-07 General Electric Company Reduced height flat spring spacer for nuclear fuel rods
US20060070477A1 (en) * 2004-10-04 2006-04-06 Roger Serzen Adaptive wheelchair joystick
US9406409B2 (en) 2013-03-06 2016-08-02 Nuscale Power, Llc Managing nuclear reactor spent fuel rods
KR101754754B1 (ko) * 2016-06-21 2017-07-07 한국원자력연구원 사용후 핵연료 건식 저장 용기
WO2018091969A1 (fr) * 2016-11-18 2018-05-24 Salvatore Moricca Affaissement contrôlé de récipient hip pour traitement de déchets

Citations (5)

* Cited by examiner, † Cited by third party
Publication number Priority date Publication date Assignee Title
FR2375696A1 (fr) * 1976-12-21 1978-07-21 Asea Ab Procede pour enfermer du combustible nucleaire use ou des dechets de combustible nucleaire
FR2375695A1 (fr) * 1976-12-21 1978-07-21 Asea Ab Procede pour le traitement de dechets radioactifs
US4115311A (en) * 1977-03-10 1978-09-19 The United States Of America As Represented By The United States Department Of Energy Nuclear waste storage container with metal matrix
FR2430651A1 (fr) * 1978-07-08 1980-02-01 Transnuklear Gmbh Couvercle compose pour conteneur blinde destine au transport et au stockage d'elements combustibles irradies
FR2432752A1 (fr) * 1978-08-03 1980-02-29 Gagneraud Francis Procede d'enrobage de dechets radioactifs en vue d'assurer le transport et le stockage en toute securite

Family Cites Families (6)

* Cited by examiner, † Cited by third party
Publication number Priority date Publication date Assignee Title
BE622903A (fr) * 1961-10-09
US4090873A (en) * 1975-01-23 1978-05-23 Nippon Gakki Seizo Kabushiki Kaisha Process for producing clad metals
JPS54130798A (en) * 1978-03-31 1979-10-11 Toshiba Corp Radioactive waste solidifying method
US4257912A (en) * 1978-06-12 1981-03-24 Westinghouse Electric Corp. Concrete encapsulation for spent nuclear fuel storage
JPS57960A (en) * 1980-06-04 1982-01-06 Takuya Yura Tricycle
GB2076582B (en) * 1981-05-13 1983-06-02 Nukem Gmbh A process for embedding radioactive waste in a metal matrix

Patent Citations (5)

* Cited by examiner, † Cited by third party
Publication number Priority date Publication date Assignee Title
FR2375696A1 (fr) * 1976-12-21 1978-07-21 Asea Ab Procede pour enfermer du combustible nucleaire use ou des dechets de combustible nucleaire
FR2375695A1 (fr) * 1976-12-21 1978-07-21 Asea Ab Procede pour le traitement de dechets radioactifs
US4115311A (en) * 1977-03-10 1978-09-19 The United States Of America As Represented By The United States Department Of Energy Nuclear waste storage container with metal matrix
FR2430651A1 (fr) * 1978-07-08 1980-02-01 Transnuklear Gmbh Couvercle compose pour conteneur blinde destine au transport et au stockage d'elements combustibles irradies
FR2432752A1 (fr) * 1978-08-03 1980-02-29 Gagneraud Francis Procede d'enrobage de dechets radioactifs en vue d'assurer le transport et le stockage en toute securite

Non-Patent Citations (1)

* Cited by examiner, † Cited by third party
Title
SPRECHSAAL, Jahrgang 113, Nr. 10, Oktober 1980, Seiten 753-764, Coburg, (DE) *

Cited By (9)

* Cited by examiner, † Cited by third party
Publication number Priority date Publication date Assignee Title
EP0077955A2 (fr) * 1981-10-28 1983-05-04 Deutsche Gesellschaft für Wiederaufarbeitung von Kernbrennstoffen mbH Container de combustibles pour le transport et/ou l'emmagasinage de combustibles nucléaires
EP0077955A3 (fr) * 1981-10-28 1983-09-07 Deutsche Gesellschaft für Wiederaufarbeitung von Kernbrennstoffen mbH Container de combustibles pour le transport et/ou l'emmagasinage de combustibles nucléaires
EP0084840A1 (fr) * 1982-01-22 1983-08-03 Deutsche Gesellschaft für Wiederaufarbeitung von Kernbrennstoffen mbH Procédé pour fermer un récipient contenant des substances radio-actives
EP0104398A1 (fr) * 1982-08-26 1984-04-04 Deutsche Gesellschaft für Wiederaufarbeitung von Kernbrennstoffen mbH Conteneur pour le stockage à sec d'éléments combustibles nucléaires épuisés
EP0141967A1 (fr) * 1983-09-24 1985-05-22 STEAG Kernenergie GmbH Procédé de fermeture d'un récipient pour le stockage de produits radioactifs
GB2151068A (en) * 1983-12-09 1985-07-10 Kernforschungsanlage Juelich Process for storing fuel elements
DE3720731A1 (de) * 1986-06-25 1988-01-07 Atomic Energy Of Australia Einkapselung von abfallstoffen
DE102004059216B3 (de) * 2004-12-09 2006-06-01 Forschungszentrum Karlsruhe Gmbh Verfahren zur Einlagerung radioaktiver Reststoffe, Behälter dafür und seine Verwendung
EP2160736A4 (fr) * 2007-05-25 2016-03-30 Swedish Metallurg And Mining Ab Réceptacle final de combustible nucléaire épuisé

Also Published As

Publication number Publication date
JPH0245839B2 (fr) 1990-10-11
FI72008C (fi) 1987-03-09
JPS57168200A (en) 1982-10-16
FI72008B (fi) 1986-11-28
SE425707B (sv) 1982-10-25
ES510536A0 (es) 1984-01-01
FI820964L (fi) 1982-09-21
SE8101778L (fr) 1982-09-21
EP0061067B1 (fr) 1985-11-13
DE3267356D1 (en) 1985-12-19
ES8402111A1 (es) 1984-01-01
CA1190332A (fr) 1985-07-09
US4491540A (en) 1985-01-01

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