EP1367602A1 - Verfahren zur Fertigung eines Behälters zum Einschluss von abgebranntem Kernbrennstoff - Google Patents

Verfahren zur Fertigung eines Behälters zum Einschluss von abgebranntem Kernbrennstoff Download PDF

Info

Publication number
EP1367602A1
EP1367602A1 EP03011841A EP03011841A EP1367602A1 EP 1367602 A1 EP1367602 A1 EP 1367602A1 EP 03011841 A EP03011841 A EP 03011841A EP 03011841 A EP03011841 A EP 03011841A EP 1367602 A1 EP1367602 A1 EP 1367602A1
Authority
EP
European Patent Office
Prior art keywords
spent fuel
neutron shield
neutron
resin
fins
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.)
Withdrawn
Application number
EP03011841A
Other languages
English (en)
French (fr)
Inventor
Kiminori Hitachi Ltd. Int. Property Group Iga
Masashi Hitachi Ltd Int. Property Group Shimizu
Mamoru Hitachi Ltd Int Property Group Kamoshida
Seigo Hitachi Ltd. Int. Property Group Domori
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.)
Hitachi Ltd
Original Assignee
Hitachi Ltd
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 Hitachi Ltd filed Critical Hitachi Ltd
Publication of EP1367602A1 publication Critical patent/EP1367602A1/de
Withdrawn legal-status Critical Current

Links

Images

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
    • G21F1/00—Shielding characterised by the composition of the materials
    • G21F1/02—Selection of uniform shielding materials
    • G21F1/10—Organic substances; Dispersions in organic carriers
    • G21F1/103—Dispersions in organic carriers
    • 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
    • G21F5/008—Containers for fuel elements

Definitions

  • the present invention relates to a spent fuel cask and a method of manufacturing the same, and more particular, to a cask for storage of a spent fuel suitable for transportation and storage of a spent fuel assembly and a method of manufacturing the same.
  • a spent fuel assembly having been used in a core of a nuclear reactor for a predetermined period of time is taken out from the core to be temporarily stored for a predetermined cooling period of time for the purpose of cooling in a spent fuel pool.
  • a spent fuel assembly, for which the predetermined cooling period of time has elapsed, is received in a spent fuel cask (for example, a metallic cask) and transported to a fuel reprocessing facility or an intermediate storage facility.
  • the spent fuel cask is provided with a radiation shield body, which shields radiation, such as neutron or the like, emitted from the received spent fuel assembly.
  • a spent fuel cask comprises an outer cylinder provided outside an inner cylinder, which constitutes a container, heat transfer fins made of carbon steel or the like and mounted on an outer surface of the inner cylinder to be spaced circumferentially at intervals, and a metallic basket formed inside the inner cylinder.
  • a cured resin being a neutron shield body is present between the outer cylinder and the inner cylinder.
  • the inner cylinder is a top-opened cylinder made of carbon steel and serves as a gamma-rays shield body.
  • the metallic basket comprises a plurality of cells, in each of which a spent fuel assembly is received. The metallic basket receives therein about 30 to 70 spent fuel assemblies in total.
  • the cask has a height of about 4.5 m and a diameter of about 2.5 m, and a total weight of the cask in a state, in which spent fuel assemblies are received therein, amounts to around 100 to 150 tons.
  • Used as a neutron shield body is a room temperature setting type epoxy resin, which ordinarily cures at room temperature, or a resin composed of silicone rubber, to which an admixture such as a powder neutron absorber and a powder refractory material is added.
  • the neutron shield body must assure a necessary neutron shielding capacity, and is mainly manufactured in the following manner.
  • An admixture such as a neutron absorber such as powder boron carbide or the like, and a refractory material such as powder aluminum hydroxide or the like are mixed in an epoxy resin or silicone rubber, which make a base material, and these materials are adequately kneaded by a mixer to be made uniform.
  • Such kneading is performed in a reduced pressure tank in order to prevent an decrease in shield capacity, caused by entrainment of an air.
  • a neutron shield body having been sufficiently kneaded is injected into a space between an inner cylinder and an outer cylinder from above in a state, in which a spent fuel cask is made upright, to cure.
  • an admixture such as a powder neutron absorber and a powder refractory material settles until a resin cures, and the admixture in an upper portion of the space is decreased in concentration, the neutron shielding capacity cannot be assured, so that there is a need of controlling viscosity of the resin, particles of the admixture, curing temperature, curing time, or the like so as to eliminate settling of the admixture.
  • JP-A-11-295483 describes injecting a resin into an upright square pipe from above and curing the same.
  • Settling of an admixture can be prevented by the use of a resin having a large viscosity. Since the use of a resin having a large viscosity leads to worsening of working efficiency at the time of injection and an increase in the number of control processes, it takes around a month to inject a resin into a single spent fuel cask and cure the same to finish a neutron shield body.
  • the invention for attaining the object has a feature in injecting a resin and a neutron absorber into a horizontal mold to cure the resin to manufacture a neutron shield body, arranging the neutron shield body having been taken out from the mold, outside an inner cylinder, to which a plurality of fins are mounted, and between the fins, and mounting an outer cylinder on the fins to cover the neutron shield body.
  • the invention for attaining the object has a feature in a spent fuel cask provided with neutron shield bodies, comprising an inner cylinder, in which a spent fuel is received, a plurality of fins provided in the inner cylinder, neutron shield bodies arranged between adjacent fins, and an outer cylinder to cover the neutron shield bodies.
  • a neutron shield body is manufactured by injecting a resin and a neutron absorber into the mold and arranged outside the inner cylinder, a period of time taken in manufacture of the neutron shield body is considerably shortened. Also, a resin and a neutron absorber are injected into a mold, which is laid horizontal, the neutron absorber is rich in the vicinity of a bottom of the mold and distributed uniformly in a lengthwise direction of the mold. Therefore, with the spent fuel cask provided with neutron shield bodies mounted thereon, the neutron absorber is present to be rich radially toward the inner cylinder, and distributed uniformly in an axial direction of the cask. Therefore, the radiation shielding capacity of the spent fuel cask is made further uniform in the axial direction of the spent fuel cask.
  • the spent fuel cask 1 comprises an inner cylinder 2 provided in an outer cylinder 3, which constitutes a container, heat transfer fins 4 made of carbon steel and mounted on an outer surface of the inner cylinder (inside container) 2 to be spaced circumferentially at intervals, and a metallic basket 6 formed inside the inner cylinder 2 in a lattice-like manner.
  • Neutron shield bodies 5 are arranged in respective spaces defined by the heat transfer fins 4 between the outer cylinder 3 and the inner cylinder 2.
  • the inner cylinder 2 is a top-opened cylinder made of carbon steel to serve as gamma-rays shield body.
  • the metallic basket 6 comprises a plurality of cells, in each of which a spent fuel assembly is received.
  • Mounted in an opening of the inner cylinder 2 is a primary lid 7 for preventing leakage of a radioactive substance, and mounted outside the lid is a secondary lid 8.
  • a neutron shield body 5 is also arranged in the primary lid 7.
  • Mounted on a side of the outer cylinder are a plurality of trunnions 9, which are used for suspension of the spent fuel cask 1.
  • a method of manufacturing a spent fuel cask will be described, in which operations are carried out in STEP 10 to STEP 18.
  • a mold 20 (Fig. 3), into which a resin being a material for the neutron shield body 5 is injected, is fabricated (STEP 10).
  • the mold 20 is constituted by mounting two long side plates 23 and two short side plates 24 to a bottom plate 22, and a portion of the mold facing the bottom plate 22 is opened. The side plates 23 and the side plates 24 are joined together.
  • a resin injection portion 21 is formed inside the mold 20.
  • the mold 20 comprises a resin injection space 21 inside.
  • the side plates 24 have the same shape as a cross sectional shape of a space (a space prior to mounting of the neutron shield body 5), which is surrounded and defined by the inner cylinder 2, the outer cylinder 3, and two opposed heat transfer fins 4, in a direction perpendicular to an axis of the spent fuel cask 1. Therefore, a longitudinal, cross sectional shape of the neutron shield body 5, which is manufactured by injecting a kneaded substance containing a resin into the resin injection space 21, is the same as a cross sectional shape of the space in the direction perpendicular to the axis of the spent fuel cask 1.
  • a distance between the opposed side plates 24 corresponds to a length of one of a plurality of sections, into which the space mounting therein the neutron shield body 5 is divided in an axial direction of the spent fuel cask 1, in view of operability at the time of manufacture of the neutron shield body 5 and at the time of handling of the body.
  • the bottom plate 22 defines a configuration of the neutron shield body 5 toward the inner cylinder 2.
  • a surface of the neutron shield body 5 on an opened side of the mold 20 will face the outer cylinder 3. Therefore, the mold 20 is shaped to diverge upward from the bottom plate 22, so that the neutron shield body 5 having been cured and formed in the mold 20 is made easy to take out.
  • an epoxy resin used for manufacture of the neutron shield body 5 is a thermosetting-type one having the thermal resistance and curing at a higher temperature than room temperature upon application of heat from outside.
  • thermosetting-type epoxy resin As a concrete thermosetting-type epoxy resin, at least one of glycidyl ether type epoxy compounds such as bisphenol A type, novolak type, or alicyclic ones, various glycidyl ester type epoxy compounds, glycidyl amine type epoxy compounds, and biphenyl type epoxy compounds, is used to serve a principal ingredient, and also at least one of amine hardening agents, such aromatic amine, alicyclic amine, polyamide amine, or the like, acid anhydride hardening agents, and imidazole hardening accelerating agents, is used as a hardening agent having the function of performing ring-opening polymerization of an epoxy radical of the principal ingredient.
  • amine hardening agents such aromatic amine, alicyclic amine, polyamide amine, or the like, acid anhydride hardening agents, and imidazole hardening accelerating agents.
  • One of the principal ingredients and the hardening agent are mixed to be used.
  • a powder neutron absorber used as a powder neutron absorber is one of boron compounds such as boron carbide, boron nitride, or the like, cadmium compounds such as cadmium oxide, or the like, gadolinium compounds such as gadolinium oxide, or the like, and samarium compounds such as samarium oxide, or the like.
  • boron compounds such as boron carbide, boron nitride, or the like
  • cadmium compounds such as cadmium oxide, or the like
  • gadolinium compounds such as gadolinium oxide, or the like
  • samarium compounds such as samarium oxide, or the like.
  • a powder refractory material used as a powder refractory material is one of metalhydroxides such as magnesium hydroxide, aluminum hydroxide, calcium hydroxide, or the like, metallic oxide hydrates, inorganic phosphoric acid compounds such as ammonium polyphosphate, or the like, organic phosphorus compounds such as phosphate ester, or the like, and halogen compounds such as hexabromobenzene, tetrabromobisphenol A, or the like.
  • metalhydroxides such as magnesium hydroxide, aluminum hydroxide, calcium hydroxide, or the like
  • metallic oxide hydrates metallic oxide hydrates
  • inorganic phosphoric acid compounds such as ammonium polyphosphate, or the like
  • organic phosphorus compounds such as phosphate ester, or the like
  • halogen compounds such as hexabromobenzene, tetrabromobisphenol A, or the like.
  • Kneading (STEP 12) is adequately carried out at reduced pressure so that the materials are uniformly mixed together by means of a mixer and an air is excluded from the kneaded substance.
  • the mold 20 is installed in a location, in which the kneaded substance obtained in STEP 12 is to be injected (STEP 13). At this time, the mold is maintained in a horizontal position with the bottom plate 22 facing downward. A mold release agent is applied on inner surfaces of the mold 20. Thereafter, the kneaded substance 25 is injected into the mold 20 (STEP 14). Injection of the kneaded substance 25 into the mold 20 is performed by means of a length of hose (or trough) 30 (see Fig. 4).
  • an operation for primary curing is carried out (STEP 15).
  • the primary curing is performed by placing the mold 20, into which the kneaded substance has been injected, in a heating furnace while keeping the mold in a horizontal position, and heating the kneaded substance in the mold 20.
  • the mold 20 may be heated by means of a heater.
  • the resin contained in the kneaded substance 25 in the mold 20 is temporarily decreased in viscosity, so that an admixture (neutron absorber and refractory material) 26 contained in the kneaded substance settles near the bottom plate 22 of the mold 20 (see Fig. 6).
  • a secondary curing is performed (STEP 16). In order to further increase the resin in polymerization degree, the secondary curing is performed to heat the kneaded substance in the mold 20 at a higher temperature than the heating temperature in the primary curing.
  • the neutron shield body 5 being a cured substance, which the kneaded substance has completely cured to generate, is taken out from the mold 20 (STEP 17).
  • the process in STEP 17 is called demolding. Since the mold release agent is applied on the inner surfaces of the mold 20, the neutron shield body 5 does not adhere to the inner surfaces of the mold 20 and can be readily taken out from the mold 20.
  • the neutron shield body 5 having been taken out from the mold 20 is mounted outside the inner cylinder 2 of the spent fuel cask 1 (STEP 18).
  • the spent fuel cask 1 with the outer cylinder 3 not mounted thereon is laid horizontally on a rotating roller of a support member (not shown) having the rotating roller. That is, both ends of the inner cylinder 2 are supported by the rotating roller.
  • a pair of shield covers 27 and the heat transfer fins 4 are mounted on outer surfaces of the inner cylinder 2.
  • One of the shield covers 27 is mounted on an upper end of the inner cylinder 2, and the other of the shield covers 27 is mounted on a lower end of the inner cylinder 2.
  • the plurality of heat transfer fins 4 are arranged between the pair of shield covers 27 and at predetermined spacings circumferentially of the inner cylinder 2.
  • the neutron shield bodies 5 are successively arranged in respective spaces 28, each of which is defined by two adjacent heat transfer fins 4 and the pair of shield covers 27.
  • the neutron shield bodies 5 are first arranged in several spaces 28, which face upward.
  • An outer cylinder member 29 is arranged in a manner to cover the neutron shield bodies 5 arranged in the spaces 28, and peripheral portions of the outer cylinder member 29 are welded to the two heat transfer fins 4 and the pair of shield covers 27.
  • the spent fuel cask 1 is rotated once to move the outer cylinder member 29 in a downward direction.
  • the neutron shield bodies 5 are arranged in several spaces 28 extending from that space 28, which is disposed adjacent the spaces 28 covered by the outer cylinder member 29 to face upward.
  • a layer of the admixture 26 having settled during the operation of primary curing in STEP 15 is present on a side of the inner cylinder 2 in a state, in which the neutron shield bodies 5 are mounted.
  • the neutron absorber constituting the admixture 26 is also present uniformly on the side of the inner cylinder 2 in an axial direction of the inner cylinder 2. Therefore, that macroscopic neutron absorption cross sectional area radially of the spent fuel cask 1, which determines the neutron shielding performance, is made substantially uniform in the axial direction of the inner cylinder 2.
  • the neutron shield body 5 mounted in the primary lid 7 is also manufactured in the procedure shown in Fig. 1. Since the neutron shield body 5 mounted in the primary lid 7 is in the form of a circular disk, however, a mold used comprises an annular side plate mounted on a circular bottom plate. The neutron shield body 5 mounted in the primary lid 7 is manufactured in the processes of STEP 11 to STEP 17 with the use of the mold. The finished neutron shield body 5 is received in a space defined in the primary lid 7. Thereafter, a circular disk is mounted on the primary lid 7 in a manner to cover the neutron shield body 5. A neutron shield body 5 (see Fig. 7(A)) mounted on the bottom of the spent fuel cask 1 is also manufactured in the same manner as the neutron shield body 5 mounted in the primary lid 7.
  • the spent fuel cask is completed in the processes of operation described above.
  • the manufacturing process of the spent fuel cask shown in Fig. 1 may comprise respective operations in STEP 11 and the following STEPs.
  • a period of time taken in manufacture of the neutron shield body 5 and mounting of the neutron shield body 5 on the inner cylinder 2 can be considerably shortened as compared with the case where a kneaded substance containing a resin is conventionally injected between the inner cylinder 2 and the outer cylinder 3. This leads to considerable shortening of a period of time taken in manufacture of a spent fuel cask 1. Also, since the neutron absorber is distributed uniformly in the axial direction of the spent fuel cask 1, the neutron shielding performance in a radial direction, of the spent fuel cask 1 can be demonstrated uniformly in the axial direction of the spent fuel cask 1.
  • the inner cylinder 2 serves as a radiation shield body to shield gamma rays emitted from a spent fuel assembly.
  • the gamma rays shielding capacity in a radial direction, of the inner cylinder 2 is made uniform in the axial direction of the spent fuel cask 1.
  • the radiation (neutron and gamma rays) shielding capacity can be made uniform in the axial direction of the spent fuel cask 1.
  • the refractory material in the neutron shield body 5 can be uniformly distributed lengthwise of the neutron shield body 5. Therefore, the refractory material can also be uniformly distributed in density of hydrogen number in the axial direction of the spent fuel cask.
  • the neutron shielding capacity of the spent fuel cask 1 is further made uniform in the axial direction of the spent fuel cask 1.
  • the neutron absorber and the refractory material in the radial direction of the spent fuel cask 1 is increased in concentration distribution toward the inner cylinder 2.
  • the embodiment makes it possible to easily insert the neutron shield bodies 5 into the spaces 28.
  • the outer cylinder members 29 are mounted on the heat transfer fins 4 to cover the neutron shield bodies.
  • the neutron shield bodies 5 having been arranged in the spaces 28 are held by the outer cylinder members 29 in the embodiment, the neutron shield bodies 5 having been arranged can be prevented from falling off from the spaces 28 in the case where the inner cylinder 2 laid in a horizontal position is rotated in order to arrange the neutron shield bodies 5 in the remaining spaces 28. Therefore, an operation of arranging the neutron shield bodies 5 in the spaces 28 can be performed efficiently. Owing to this, a period of time taken in manufacture of a spent fuel cask 1 can be further shortened.
  • a period of time taken in manufacture of a spent fuel cask can be shortened, and besides the radiation shielding capacity in a radial direction, of a spent fuel cask can be made further uniform in an axial direction of a finished spent fuel cask.
EP03011841A 2002-05-31 2003-05-26 Verfahren zur Fertigung eines Behälters zum Einschluss von abgebranntem Kernbrennstoff Withdrawn EP1367602A1 (de)

Applications Claiming Priority (2)

Application Number Priority Date Filing Date Title
JP2002158504A JP2003344581A (ja) 2002-05-31 2002-05-31 使用済燃料用キャスク及びその製造方法
JP2002158504 2002-05-31

Publications (1)

Publication Number Publication Date
EP1367602A1 true EP1367602A1 (de) 2003-12-03

Family

ID=29417239

Family Applications (1)

Application Number Title Priority Date Filing Date
EP03011841A Withdrawn EP1367602A1 (de) 2002-05-31 2003-05-26 Verfahren zur Fertigung eines Behälters zum Einschluss von abgebranntem Kernbrennstoff

Country Status (2)

Country Link
EP (1) EP1367602A1 (de)
JP (1) JP2003344581A (de)

Cited By (1)

* Cited by examiner, † Cited by third party
Publication number Priority date Publication date Assignee Title
CN111627575A (zh) * 2020-06-11 2020-09-04 中国原子能科学研究院 用于反应堆的屏蔽组件及其屏蔽结构

Families Citing this family (2)

* Cited by examiner, † Cited by third party
Publication number Priority date Publication date Assignee Title
JP4621581B2 (ja) * 2005-11-14 2011-01-26 株式会社東芝 キャスク用レジン及びその充填方法
FR2974228B1 (fr) * 2011-04-18 2013-06-07 Tn Int Element de conduction thermique permettant d'ameliorer la fabrication d'un emballage de transport et/ou d'entreposage de matieres radioactives

Citations (10)

* Cited by examiner, † Cited by third party
Publication number Priority date Publication date Assignee Title
DE2065863A1 (de) * 1969-08-13 1976-09-23 Transnucleaire Behaelter fuer radioaktive materialien
FR2471028A1 (fr) * 1979-11-17 1981-06-12 Transnuklear Gmbh Blindage anti-neutrons
GB2198682A (en) * 1986-12-19 1988-06-22 British Nuclear Fuels Plc Flask for receiving radioactive material
JPH06180388A (ja) * 1992-12-11 1994-06-28 Sanoya Sangyo Kk 耐熱性中性子遮蔽材
DE4402282C1 (de) * 1994-01-27 1995-04-13 Apparate Und Anlagenbau Gmbh Verfahren zur Herstellung einer Schweißverbindung und nach diesem Verfahren hergestellter Transport- und Lagerbehälter für abgebrannte Kernbrennstoffkassetten
FR2726394A1 (fr) * 1994-10-27 1996-05-03 Amco Brique en plomb munie d'un revetement resistant et procede d'application du revetement
EP0942435A1 (de) * 1998-03-13 1999-09-15 Societe Pour Les Transports De L'industrie Nucleaire Transnucleaire Strahlenschutzvorrichtung für Behälter zum Transport von radioaktiven Stoffen
JP2001021684A (ja) * 1999-07-06 2001-01-26 Mitsubishi Heavy Ind Ltd 使用済燃料輸送貯蔵用キャスク、放射線遮蔽体及びその形成方法
EP1083577A1 (de) * 1999-09-09 2001-03-14 Mitsubishi Heavy Industries, Ltd. Behälter, Herstellungsverfahren dafür und Formteil
JP2002055195A (ja) * 2000-08-11 2002-02-20 Mitsubishi Heavy Ind Ltd キャスクおよびキャスクの製造方法

Patent Citations (10)

* Cited by examiner, † Cited by third party
Publication number Priority date Publication date Assignee Title
DE2065863A1 (de) * 1969-08-13 1976-09-23 Transnucleaire Behaelter fuer radioaktive materialien
FR2471028A1 (fr) * 1979-11-17 1981-06-12 Transnuklear Gmbh Blindage anti-neutrons
GB2198682A (en) * 1986-12-19 1988-06-22 British Nuclear Fuels Plc Flask for receiving radioactive material
JPH06180388A (ja) * 1992-12-11 1994-06-28 Sanoya Sangyo Kk 耐熱性中性子遮蔽材
DE4402282C1 (de) * 1994-01-27 1995-04-13 Apparate Und Anlagenbau Gmbh Verfahren zur Herstellung einer Schweißverbindung und nach diesem Verfahren hergestellter Transport- und Lagerbehälter für abgebrannte Kernbrennstoffkassetten
FR2726394A1 (fr) * 1994-10-27 1996-05-03 Amco Brique en plomb munie d'un revetement resistant et procede d'application du revetement
EP0942435A1 (de) * 1998-03-13 1999-09-15 Societe Pour Les Transports De L'industrie Nucleaire Transnucleaire Strahlenschutzvorrichtung für Behälter zum Transport von radioaktiven Stoffen
JP2001021684A (ja) * 1999-07-06 2001-01-26 Mitsubishi Heavy Ind Ltd 使用済燃料輸送貯蔵用キャスク、放射線遮蔽体及びその形成方法
EP1083577A1 (de) * 1999-09-09 2001-03-14 Mitsubishi Heavy Industries, Ltd. Behälter, Herstellungsverfahren dafür und Formteil
JP2002055195A (ja) * 2000-08-11 2002-02-20 Mitsubishi Heavy Ind Ltd キャスクおよびキャスクの製造方法

Non-Patent Citations (3)

* Cited by examiner, † Cited by third party
Title
PATENT ABSTRACTS OF JAPAN vol. 018, no. 519 (P - 1807) 29 September 1994 (1994-09-29) *
PATENT ABSTRACTS OF JAPAN vol. 2000, no. 16 8 May 2001 (2001-05-08) *
PATENT ABSTRACTS OF JAPAN vol. 2002, no. 06 4 June 2002 (2002-06-04) *

Cited By (2)

* Cited by examiner, † Cited by third party
Publication number Priority date Publication date Assignee Title
CN111627575A (zh) * 2020-06-11 2020-09-04 中国原子能科学研究院 用于反应堆的屏蔽组件及其屏蔽结构
CN111627575B (zh) * 2020-06-11 2022-07-01 中国原子能科学研究院 用于反应堆的屏蔽组件及其屏蔽结构

Also Published As

Publication number Publication date
JP2003344581A (ja) 2003-12-03

Similar Documents

Publication Publication Date Title
US8995604B2 (en) System, method and apparatus for providing additional radiation shielding to high level radioactive materials
US6718000B2 (en) Ventilated vertical overpack
JP3951685B2 (ja) 中性子遮蔽材及び使用済み燃料収納容器
US20100284506A1 (en) Apparatus for storing and/or transporting high level radioactive waste, and method for manufacturing the same
US20060120500A1 (en) Method and system for storing nuclear fuel
JP7121856B2 (ja) 使用済み核燃料の貯蔵と輸送のための多部品キャスク
EP0175140B1 (de) Lagerbehälter für verbrauchten Kernbrennstoff mit zusammenhängendem Einsatzkorb
US6605817B1 (en) Neutron shield and cask that uses the neutron shield
US3828197A (en) Radioactive waste storage
US9336914B2 (en) Radioactive waste solidification method
US20020003851A1 (en) Systems and methods for storing exothermic materials
EP1367602A1 (de) Verfahren zur Fertigung eines Behälters zum Einschluss von abgebranntem Kernbrennstoff
JP4567839B2 (ja) 放射性物質貯蔵設備
JP4082179B2 (ja) 使用済核燃料収納容器
JP4783197B2 (ja) 金属キャスクおよびその製造方法
JP4686437B2 (ja) 金属キャスクの中性子遮へい材の施工方法およびその施工方法により製作された金属キャスク
JP2001021684A (ja) 使用済燃料輸送貯蔵用キャスク、放射線遮蔽体及びその形成方法
JP2007033059A (ja) 中性子遮蔽材および使用済み燃料収納容器
US6771731B2 (en) Device for storage of hazardous material
CN112313756B (zh) 用于存储和运输乏核燃料的多部件桶
JPH1184068A (ja) 放射性物質の貯蔵設備
JP2003270382A (ja) 放射性物質格納容器および放射性物質の格納方法
US20030138070A1 (en) Device for storage of hazardous material
EP4352753A2 (de) Stapelbares lagersystem für nuklearabfälle
RU2277730C1 (ru) Активная зона уран-графитового высокотемпературного ядерного реактора

Legal Events

Date Code Title Description
PUAI Public reference made under article 153(3) epc to a published international application that has entered the european phase

Free format text: ORIGINAL CODE: 0009012

AK Designated contracting states

Kind code of ref document: A1

Designated state(s): AT BE BG CH CY CZ DE DK EE ES FI FR GB GR HU IE IT LI LU MC NL PT RO SE SI SK TR

AX Request for extension of the european patent

Extension state: AL LT LV MK

17P Request for examination filed

Effective date: 20040525

AKX Designation fees paid

Designated state(s): DE ES FR

STAA Information on the status of an ep patent application or granted ep patent

Free format text: STATUS: THE APPLICATION IS DEEMED TO BE WITHDRAWN

18D Application deemed to be withdrawn

Effective date: 20060503