EP0082467B1 - Behälter für die Langzeitlagerung von abgebrannten Kernreaktorbrennelementen - Google Patents

Behälter für die Langzeitlagerung von abgebrannten Kernreaktorbrennelementen Download PDF

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Publication number
EP0082467B1
EP0082467B1 EP82111612A EP82111612A EP0082467B1 EP 0082467 B1 EP0082467 B1 EP 0082467B1 EP 82111612 A EP82111612 A EP 82111612A EP 82111612 A EP82111612 A EP 82111612A EP 0082467 B1 EP0082467 B1 EP 0082467B1
Authority
EP
European Patent Office
Prior art keywords
container
main body
closure cover
weld
cover
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
EP82111612A
Other languages
German (de)
English (en)
French (fr)
Other versions
EP0082467A1 (de
Inventor
Franz-Wolfgang Dipl.-Ing. Dr. Popp
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.)
Deutsche Gesellschaft fuer Wiederaufarbeitung von Kernbrennstoffen mbH
Original Assignee
Deutsche Gesellschaft fuer Wiederaufarbeitung von Kernbrennstoffen mbH
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 Deutsche Gesellschaft fuer Wiederaufarbeitung von Kernbrennstoffen mbH filed Critical Deutsche Gesellschaft fuer Wiederaufarbeitung von Kernbrennstoffen mbH
Publication of EP0082467A1 publication Critical patent/EP0082467A1/de
Application granted granted Critical
Publication of EP0082467B1 publication Critical patent/EP0082467B1/de
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
    • 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
    • Y10—TECHNICAL SUBJECTS COVERED BY FORMER USPC
    • Y10S—TECHNICAL SUBJECTS COVERED BY FORMER USPC CROSS-REFERENCE ART COLLECTIONS [XRACs] AND DIGESTS
    • Y10S220/00—Receptacles
    • Y10S220/917—Corrosion resistant container

Definitions

  • the invention relates to a container made of steel or cast steel for the long-term storage of spent nuclear reactor fuel elements or other radioactive materials, the front opening of which is closed by a welded-on sealing cap.
  • the container After such a container has been filled with the irradiated nuclear reactor fuel elements, the container must be tightly closed by a cover.
  • a cover In the case of a metallic container body, it is possible to close it tightly by welding in a metallic lid. If the main body of the container is made of graphite, the main body of the container can be closed at high temperature and high pressure with a sealing cover, which is also made of graphite.
  • Long-term storage containers must be mechanically stable, corrosion-resistant and tightly sealed. If the main body of the container is made of steel, the mechanical stability and tight sealing is guaranteed by welding the main body of the container and the sealing cover.
  • the corrosion resistance of the steel is, however, insufficient for the purpose of long-term storage, for example final storage in salt rock. It has therefore already been proposed to produce a container for long-term storage from graphite which has very good corrosion resistance. However, the mechanical stability compared to a steel container is lower.
  • the container were made of steel or cast steel to achieve mechanical stability and had a corrosion-resistant protective layer made of graphite, ceramic or enamel on the outside. So far this has stood in the way of the fact that after welding the container in the hot cell in this hot cell, a perfect corrosion coating can only be carried out with great technical effort by means of remotely operated handling devices.
  • the invention has for its object to provide a container of the type described above, the base material of which has mechanical stability and which is corrosion-resistant by means of an outer coating and which enables the container to be easily closed in the hot cell.
  • the object is achieved by the features specified in the characterizing part of claim 1.
  • the container body and the sealing cap are separately provided with the weld cladding before use in the hot cell.
  • the weld cladding is applied by build-up welding, which is a well-known technique (Handbuch der Sch spatechnik, J. Ruge, 2nd edition, vol. 1 "Materials", Springer Verlag, Berlin, Heidelberg, New York 1980, p. 170 ).
  • the container body and the sealing lid are coated separately with the corrosion protection layer. The invention has made it possible to carry out this coating outside the hot cell.
  • a cold-weldable material is understood to mean a material that can be welded without subsequent heat treatment. With such materials, no significant stresses or structural changes occur during welding, which have to be compensated for by an additional, subsequent heat treatment.
  • One such material is Ni Mo 16 Cr 16 Ti (trade name: Hastelloy C-4).
  • the approach of the respective welding plating on the sealing lid or on the container body is covered by the corrosion protection layer, so that the container is covered by a corrosion protection layer without a continuous gap.
  • a further advantageous embodiment of the invention is characterized by the features mentioned in claim 2.
  • the weld plating on the container base body is formed from a ring with an L-shaped cross section, which surrounds the container base body at its front end.
  • One end of the annular welding plating of the closure lid lies on an obliquely running annular surface, which lies opposite the joining surface of the container base body on the end face.
  • the fuel assembly container shown in FIG. 1 has a container body 1 which is cylindrical and is open at one end. This forms a receiving opening 2 for loading with the fuel elements, not shown here.
  • a welding plating 3 made of an annular, cross-sectionally L-shaped strip made of cold-weldable and corrosion-resistant material is applied to the end-face joining surface 10.
  • a such a material is an alloy Ni Mo 16 Cr 16 Ti (trade name: Hastelloy C-4).
  • the ring-shaped material strip applied by build-up welding is L-shaped, the short leg 4 lying on the front end of the container body 1.
  • the longer leg 5 is located on the outside of the container body 1.
  • the container body 1 is closed by a welded closure cap 6.
  • This cover 6 has an upwardly projecting edge 7.
  • the closure cover 6 is chamfered in a circular shape, the width of the projected oblique ring surface 8 extending from the inside diameter to the outside diameter of the container body 1.
  • the sealing cover 6 is circumferentially surrounded by a weld cladding 9 of a cold-weldable material.
  • the weld-plated material strip 9 comprises the edge 7 at one end and the ring surface 8 of the closure cover 6 at the other end.
  • the sealing cover 6 and the container body 1 were each coated with a corrosion protection layer 11, 12 made of graphite after their welding plating. These corrosion protection layers 11, 12 leave the welding claddings 3, 9 free in the welding area. Only the ends of the weld cladding 3 and 9 facing away from the welding area are somewhat covered by the corrosion protection layers 11, 12. A continuous gap to the container body is avoided.
  • the oblique annular surface 8 of the cover 6 creates an outwardly opening wedge gap, which receives the V-shaped weld seam 13 made of corrosion-resistant metallic material.
  • the fuel assembly container shown in FIG. 2 has a modified arrangement of the weld cladding in the joining area between the container body and the closure cover.
  • the weld plating 23 consists of an annular layer welded onto the outside of the container base body 21. This welding cladding 23 closes at the end with the end of the container body 21.
  • the weld plating 29 of the closure cover 26 only extends to the lower end of the outer circumference of the closure cover.
  • the oblique ring surface 28 does not carry any welding cladding.
  • the joining surfaces 28 and 30 form a wedge gap, but have no weld cladding.
  • a second weld seam 37 is applied, which connects the two weld claddings 23 and 29 of the closure cover 26 and the container base body 21 to one another.
  • the welding material of the second weld 37 is also made of cold-weldable, corrosion-resistant material, such as. B. Hastelloy C-4. Both welds 36 and 37 are created in the hot cell after loading the fuel assembly container. The corrosion protection layers 31 and 32 remain intact.
  • This container body 42 has a cylindrical cross section and forms a receiving opening 43 through which the container body can be loaded with radioactive substances.
  • a closure cover 44 is arranged in the receiving opening 43.
  • This cap 44 has a peripheral edge 41 which rises from the flat surface 45 of the cap 44.
  • the closure cover 44 has a U-shaped configuration when viewed in cross section, the outer surface 48 of the edge 41 tending to the axis of the closure cover 44.
  • the closure lid 44 lies with a vertical part 46 of its peripheral surface 46, 48 on the inner surface 47 of the wall 40 of the container body 42.
  • the edge 41 of the closure lid 44 is inclined to the axis of the lid and thus forms a wedge gap with the wall 40 of the container body 42 for receiving a weld seam 50.
  • Sealing lid 44 and container, base body 42 have weld claddings 52 and 53 in their joining area.
  • the weld plating 52 of the closure lid 44 extends from the inclined surface 48 over the edge 41 to the cover surface 45.
  • the weld plating 53 of the container base body 42 encompasses the open wall end of the container base body 42, the weld plating 53 extending from the outer surface via the end face to the inner surface 47 extends: the container body 42 and the closure cover 44 are provided with corrosion protection layers 54 and 55, each of which covers the end of the weld cladding 52, 53 facing away from the weld seam 50.
  • closure lid 44 After loading the container body 42 with the spent nuclear fuel elements, the closure lid 44 is inserted.
  • the closure lid 44 and the container base body 42 are connected to one another by forming the weld seam 50.
  • the invention has the great advantage that the fuel assembly container is completely covered by an anti-corrosion layer after loading.
  • the container base body and the closure lid are provided with a corrosion-resistant, cold-weldable, metallic material applied by build-up welding, while the remaining outer surface is covered by known ceramic protective layers.
  • the ceramic protective layers do not suffer any damage when welded, since metallic corrosion protection layers are present in the joining area and are connected to one another. It is after loading the fuel assembly with the nuclear fuel only one welding process is required in the hot cell; a complex, remote-controlled application of a complete corrosion protection layer is no longer necessary.

Landscapes

  • Physics & Mathematics (AREA)
  • Engineering & Computer Science (AREA)
  • General Engineering & Computer Science (AREA)
  • High Energy & Nuclear Physics (AREA)
  • Butt Welding And Welding Of Specific Article (AREA)
  • Closures For Containers (AREA)
  • Chemically Coating (AREA)
  • Monitoring And Testing Of Nuclear Reactors (AREA)
EP82111612A 1981-12-17 1982-12-14 Behälter für die Langzeitlagerung von abgebrannten Kernreaktorbrennelementen Expired EP0082467B1 (de)

Applications Claiming Priority (2)

Application Number Priority Date Filing Date Title
DE3149945 1981-12-17
DE19813149945 DE3149945A1 (de) 1981-12-17 1981-12-17 Behaelter fuer die langzeitlagerung von abgebrannten kernreaktorbrennelementen

Publications (2)

Publication Number Publication Date
EP0082467A1 EP0082467A1 (de) 1983-06-29
EP0082467B1 true EP0082467B1 (de) 1985-08-07

Family

ID=6148942

Family Applications (1)

Application Number Title Priority Date Filing Date
EP82111612A Expired EP0082467B1 (de) 1981-12-17 1982-12-14 Behälter für die Langzeitlagerung von abgebrannten Kernreaktorbrennelementen

Country Status (7)

Country Link
US (1) US4596688A (enrdf_load_stackoverflow)
EP (1) EP0082467B1 (enrdf_load_stackoverflow)
JP (1) JPS58144800A (enrdf_load_stackoverflow)
BR (1) BR8207346A (enrdf_load_stackoverflow)
CA (1) CA1187632A (enrdf_load_stackoverflow)
DE (2) DE3149945A1 (enrdf_load_stackoverflow)
ES (1) ES8404554A1 (enrdf_load_stackoverflow)

Families Citing this family (28)

* Cited by examiner, † Cited by third party
Publication number Priority date Publication date Assignee Title
DE3231747A1 (de) * 1982-08-26 1984-03-01 Deutsche Gesellschaft für Wiederaufarbeitung von Kernbrennstoffen mbH, 3000 Hannover Trockenlagerbuechse fuer abgebrannte kernreaktorbrennelemente
JPS60158399A (ja) * 1984-01-09 1985-08-19 ウエスチングハウス　エレクトリック　コ−ポレ−ション 鋳鉄製容器
DE3447278A1 (de) * 1984-12-22 1986-06-26 Kernforschungszentrum Karlsruhe Gmbh, 7500 Karlsruhe Langzeitbestaendige korrosionsschutzumhuellung fuer dicht verschlossene gebinde mit hochradioaktivem inhalt
GB2176925A (en) * 1985-06-19 1987-01-07 Us Energy Waste disposal package
US4700863A (en) * 1986-01-09 1987-10-20 The United States Of America As Represented By The United States Department Of Energy Seal welded cast iron nuclear waste container
DE3632270A1 (de) * 1986-09-23 1988-04-07 Wiederaufarbeitung Von Kernbre Verfahren und vorrichtung zum beladen und verschliessen eines doppelbehaeltersystems fuer die lagerung von radioaktivem material sowie verschluss fuer das doppelbehaeltersystem
DE4204527C2 (de) * 1992-02-15 1993-12-23 Siempelkamp Gmbh & Co Verfahren zum Herstellen eines Abschirm-Transportbehälters für bestrahlte Kernreaktorbrennelemente
US5391887A (en) * 1993-02-10 1995-02-21 Trustees Of Princeton University Method and apparatus for the management of hazardous waste material
US5995573A (en) * 1996-09-18 1999-11-30 Murray, Jr.; Holt A. Dry storage arrangement for spent nuclear fuel containers
US6823034B1 (en) * 1999-03-31 2004-11-23 The United States Of America As Represented By The United States Department Of Energy Closure mechanism and method for spent nuclear fuel canisters
JP4064646B2 (ja) * 2001-06-29 2008-03-19 三菱重工業株式会社 放射性物質の密閉容器、密閉容器の密閉溶接方法、および密閉溶接方法に用いる排気装置
WO2003075285A1 (fr) * 2002-03-06 2003-09-12 Yuri Sergeyevich Alexeyev Conteneur de protection
US7165672B2 (en) 2002-10-17 2007-01-23 Mallinckrodt Inc. Polymer pharmaceutical pig and associated method of use and associated method of production
USD488864S1 (en) 2002-11-06 2004-04-20 Mallinckrodt Inc. Radioactive container
US20050286674A1 (en) * 2004-06-29 2005-12-29 The Regents Of The University Of California Composite-wall radiation-shielded cask and method of assembly
US8437444B2 (en) * 2005-01-13 2013-05-07 Nac International, Inc. Apparatus and methods for achieving redundant confinement sealing of a spent nuclear fuel canister
CN104801476A (zh) * 2008-09-24 2015-07-29 杰富意钢铁株式会社 防锈钢板及其制造方法
RU2430435C1 (ru) * 2009-12-24 2011-09-27 Валентин Александрович Жабрев Контейнер для длительного захоронения вредных отходов
US11373774B2 (en) 2010-08-12 2022-06-28 Holtec International Ventilated transfer cask
WO2014105977A1 (en) * 2012-12-26 2014-07-03 Holtec International, Inc. A radioactive material storage canister and method for sealing same
US11887744B2 (en) 2011-08-12 2024-01-30 Holtec International Container for radioactive waste
USD690350S1 (en) 2010-12-10 2013-09-24 Kabushiki Kaisha Sato Thermal head
CN104272398A (zh) 2012-04-18 2015-01-07 霍尔泰克国际股份有限公司 高放射性废料的存储和/或运输
JP2015088643A (ja) * 2013-10-31 2015-05-07 セイコーエプソン株式会社 電子デバイスの製造方法、電子デバイス、電子機器、移動体、および蓋体
JP2015087282A (ja) * 2013-10-31 2015-05-07 セイコーエプソン株式会社 電子デバイスの製造方法、電子デバイス、電子機器、移動体、および蓋体
JP2015088644A (ja) * 2013-10-31 2015-05-07 セイコーエプソン株式会社 電子デバイスの製造方法、電子デバイス、電子機器、移動体、および蓋体
CN105957573B (zh) * 2016-06-27 2018-01-30 中电投远达环保工程有限公司重庆科技分公司 放射性废水处理工艺的袋式滤料换料装置
US10494825B2 (en) * 2018-01-12 2019-12-03 Ping Kun Wang Joint compound container

Family Cites Families (18)

* Cited by examiner, † Cited by third party
Publication number Priority date Publication date Assignee Title
US3016463A (en) * 1958-04-28 1962-01-09 Smith Corp A O Multi-layer vessel having a neutron absorbing layer
US3046403A (en) * 1959-04-17 1962-07-24 Babcock & Wilcox Co Device for the storage of a heat evolving material
FR1278475A (fr) * 1961-01-26 1961-12-08 Récipients pour la destruction ou l'emmagasinage des déchets radioactifs
US3163501A (en) * 1961-10-13 1964-12-29 Bbc Brown Boveri & Cie Process for the production of welded seams in niobium and vanadium steels, and welded joints produced thereby
DE1752606A1 (de) * 1968-06-21 1971-07-08 Mannesmann Ag Verfahren zum Verschweissen von sich stumpf stossenden titanplattierten Stahlblechen
GB1288298A (enrdf_load_stackoverflow) * 1968-12-28 1972-09-06
DE1947398C3 (de) * 1969-09-19 1975-01-23 Alfa-Laval Bergedorfer Eisenwerke Gmbh, 2050 Hamburg Verfahren zum druckfesten, IdtrIBfrelen Verschweißen von Messinglegierungen
US4106179A (en) * 1973-07-16 1978-08-15 Richard Bleckmann Method of cold-joining metal parts
FR2375695A1 (fr) * 1976-12-21 1978-07-21 Asea Ab Procede pour le traitement de dechets radioactifs
SE406131B (sv) * 1977-06-10 1979-01-22 Asea Ab Sett att omge en keramisk kapsel med ett gastett holje
DE7737499U1 (de) * 1977-12-09 1978-05-24 Steag Kernenergie Gmbh, 4300 Essen Abschirmtransport- und/oder abschirmlagerbehaelter fuer radioaktive abfaelle
DE2804828A1 (de) * 1978-02-04 1979-08-09 Nukem Gmbh Stahlbehaelter zur aufnahme abgebrannter brennelemente
US4245698A (en) * 1978-03-01 1981-01-20 Exxon Research & Engineering Co. Superalloys having improved resistance to hydrogen embrittlement and methods of producing and using the same
DE2930991C2 (de) * 1979-07-31 1984-04-05 Nukem Gmbh, 6450 Hanau Behälter zur Aufnahme und Lagerung abgebrannter Brennelemente
HU179174B (en) * 1979-09-14 1982-08-28 Eroemue Es Halozattervezoe Process and apparatus for transferring and housing radioactive and/or other dangerous materials
DE2942092C2 (de) * 1979-10-18 1985-01-17 Steag Kernenergie Gmbh, 4300 Essen Endlagerbehälter für radioaktive Abfallstoffe, insbesondere bestrahlte Kernreaktorbrennelemente
DE3012256A1 (de) * 1980-03-29 1981-10-15 Transnuklear Gmbh, 6450 Hanau Behaelter zum transport und/oder lagerung radioaktiver stoffe
US4354133A (en) * 1980-08-29 1982-10-12 The United States Of America As Represented By The Secretary Of The Army Hermetically sealed container

Also Published As

Publication number Publication date
CA1187632A (en) 1985-05-21
DE3149945A1 (de) 1983-07-21
JPH0226760B2 (enrdf_load_stackoverflow) 1990-06-12
ES518748A0 (es) 1984-04-16
DE3265299D1 (en) 1985-09-12
US4596688A (en) 1986-06-24
JPS58144800A (ja) 1983-08-29
ES8404554A1 (es) 1984-04-16
EP0082467A1 (de) 1983-06-29
BR8207346A (pt) 1983-10-18

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