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WO2018131379A1 - Barre de commande pour réacteur nucléaire et son procédé de fabrication - Google Patents

Barre de commande pour réacteur nucléaire et son procédé de fabrication Download PDF

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Publication number
WO2018131379A1
WO2018131379A1 PCT/JP2017/045029 JP2017045029W WO2018131379A1 WO 2018131379 A1 WO2018131379 A1 WO 2018131379A1 JP 2017045029 W JP2017045029 W JP 2017045029W WO 2018131379 A1 WO2018131379 A1 WO 2018131379A1
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WO
WIPO (PCT)
Prior art keywords
region
control rod
blade
nuclear reactor
neutron absorber
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.)
Ceased
Application number
PCT/JP2017/045029
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English (en)
Japanese (ja)
Inventor
貴大 石嵜
祐策 丸野
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
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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 WO2018131379A1 publication Critical patent/WO2018131379A1/fr
Anticipated expiration legal-status Critical
Ceased legal-status Critical Current

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    • G—PHYSICS
    • G21—NUCLEAR PHYSICS; NUCLEAR ENGINEERING
    • G21C—NUCLEAR REACTORS
    • G21C21/00—Apparatus or processes specially adapted to the manufacture of reactors or parts thereof
    • G21C21/18—Manufacture of control elements covered by group G21C7/00
    • G—PHYSICS
    • G21—NUCLEAR PHYSICS; NUCLEAR ENGINEERING
    • G21C—NUCLEAR REACTORS
    • G21C7/00—Control of nuclear reaction
    • G21C7/06—Control of nuclear reaction by application of neutron-absorbing material, i.e. material with absorption cross-section very much in excess of reflection cross-section
    • G21C7/08—Control of nuclear reaction by application of neutron-absorbing material, i.e. material with absorption cross-section very much in excess of reflection cross-section by displacement of solid control elements, e.g. control rods
    • G21C7/10—Construction of control elements
    • G—PHYSICS
    • G21—NUCLEAR PHYSICS; NUCLEAR ENGINEERING
    • G21C—NUCLEAR REACTORS
    • G21C7/00—Control of nuclear reaction
    • G21C7/06—Control of nuclear reaction by application of neutron-absorbing material, i.e. material with absorption cross-section very much in excess of reflection cross-section
    • G21C7/08—Control of nuclear reaction by application of neutron-absorbing material, i.e. material with absorption cross-section very much in excess of reflection cross-section by displacement of solid control elements, e.g. control rods
    • G21C7/10—Construction of control elements
    • G21C7/113—Control elements made of flat elements; Control elements having cruciform cross-section
    • 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 present invention relates to a control rod for a nuclear reactor and a manufacturing method thereof.
  • a control rod for a boiling water reactor is one of in-reactor equipment that is used when the boiling water reactor is shut down or when the core power is adjusted.
  • the structure of a general control rod is as follows.
  • the control rod has a cross-shaped cross section, and the appearance of the control rod is such that the wings extend from the cross-shaped axis.
  • the axial portion is called a tie rod, and the wing portion is called a blade.
  • the control rod is inserted between the four fuel assemblies loaded in the core. When the reactor starts up, the control rod is pulled out of the core.
  • control rods other than the control rods used for adjusting the reactor core output are in a state of being pulled out of the core. In an emergency, all control rods are inserted using water pressure (reactor scram).
  • the control rod for the boiling water reactor further has a U-shaped sheath provided so as to surround each blade.
  • a neutron absorber (boron carbide powder, hafnium round bar or plate) is suspended from the handle and held in the space surrounded by the tie rod and blade and the sheath.
  • the handle and sheath are generally secured to the tie rod by welding.
  • a part of the sheath is provided with a hole for cooling the encapsulated neutron absorber.
  • SUS316L which is mainly austenitic stainless steel
  • This material is known to have stress corrosion cracking (hereinafter referred to as “SCC”) sensitivity in a specific environment.
  • SCC stress corrosion cracking
  • IASCC Irradiation Assisted Stress Corrosion Cracking
  • IASCC is said to occur when three conditions of material factors, mechanical factors, and environmental factors are met at the same time. Furthermore, in IACC, in addition to the above three factors, the amount of neutron irradiation is added as a generation factor. As a material factor, it is considered that the impurity carbon generates chromium (Cr) carbide at the time of welding, which is a cause of SCC, and measures to reduce the impurity carbon have been taken. Since mechanical factors are known to occur under tensile stress, measures have been taken by compressing surface stress by peening and polishing. As for environmental factors, the hydrogen injection method and the noble metal injection method have been performed because of the dissolved oxygen concentration and chloride ions.
  • Patent Document 1 includes a plurality of segments that are cross-shaped in cross section and are joined together by welding and arranged in the axial direction.
  • the first segment which is the uppermost segment, is processed from a single metal plate to form a handle portion and a plurality of neutron absorber filling holes extending in the axial direction and filled with a neutron absorber.
  • a pair of blade elements each having a plurality of neutron absorber filling portions are combined in a cross shape, and the second segment, which is the lowest segment, extends in the lower support portion and the axial direction and is filled with neutron absorbers
  • a pair of blade elements each having a plurality of neutron absorber filling portions forming a plurality of neutron absorber filling holes formed in a cross shape
  • the at least one third segment, which is another segment disposed between the segment and the second segment, extends in the axial direction and forms a plurality of neutron absorber filling holes filled with the neutron absorber.
  • a control rod comprising a neutron absorbing material filling portion combined in a cross shape, and joining the segments to each other by welding the neutron absorbing material filling portions of adjacent segments is disclosed. Yes. According to Patent Document 1, since welding for joining the handle portion and the neutron absorbing material filling portion is not required, it is said that irradiation-induced stress corrosion cracking of the control rod can be prevented.
  • the control rod shown in Patent Document 1 is a segment in which a stainless steel plate material constituting a blade is divided in the axial direction, each segment is provided with a vertical hole, and the vertical hole is filled with a neutron absorbing material.
  • the control rod is completed by welding the joints.
  • Each segment is further provided with a bridge for connecting to the blades facing each other, and the bridge is joined by welding.
  • the control rod since the control rod is divided in the length direction, long hole processing is not required, and high processing accuracy can be exhibited.
  • the segments are joined by welding, the possibility of occurrence of SCC and IASCC starting from the welded portion cannot be sufficiently excluded.
  • control rod for a nuclear reactor that eliminates a gap and a weld and can prevent SCC and IASCC.
  • the present invention is provided at one of a blade region having a neutron absorber filling hole, a tie rod region that supports the blade region, and an end portion in the longitudinal direction of each of the blade region and the tie rod region.
  • the control rod for a nuclear reactor is characterized in that the control rod is constituted by one member having a handle region, and the member has a melt-solidified structure.
  • the present invention is a method of manufacturing a control rod for a reactor having the above-described features, and is manufactured by metal additive manufacturing in the order of a blade region and a tie rod region from a handle region serving as an upper end of the control rod.
  • a method for manufacturing a control rod for a nuclear reactor is provided.
  • a reactor control rod capable of preventing SCC and IASCC by eliminating gaps and welds and a method for manufacturing such a reactor control rod.
  • FIG. 1 is a schematic cross-sectional view illustrating an example of a nuclear reactor control rod and a fuel assembly according to Embodiment 1.
  • FIG. It is a cross-sectional schematic diagram which shows the other example of the front-end
  • FIG. 4 is a cross-sectional schematic diagram which shows the other example of the control rod for nuclear reactors and fuel assembly which concerns on this invention.
  • FIG. 4 is a schematic diagram enlarging one blade region of FIG. 3.
  • FIG. 2 is a cross-sectional view taken along line AA ′ in FIG. 1. 2 is an electron microscope observation photograph of a prototype manufactured in Example 1.
  • FIG. 4 is a diagram showing an XRD pattern of a deposit of a prototype manufactured in Example 1.
  • FIG. 6 is a cross-sectional view of a nuclear reactor control rod according to Embodiment 2.
  • FIG. It is a flowchart which shows an example of the manufacturing method of the control rod for reactors which concerns on this
  • control rod the nuclear reactor control rod
  • the nuclear reactor control rod is roughly divided into members constituting a tie rod, a blade, and a handle.
  • these members were individually prepared and joined by welding or the like, the gaps and welds existing between the members could not be excluded, and the SCC was started from the gaps and welds. And IASCC may occur.
  • the members constituting the tie rod, the blade and the handle are integrated by a metal additive manufacturing method using metal powder as a raw material (also simply referred to as “additive additive manufacturing method” or “three-dimensional metal additive manufacturing method”).
  • a control rod (also referred to as “integral molded product” or “seamless control rod”) is produced. According to such a structure, a clearance part and a welding part can be excluded reliably in the area
  • the metal additive manufacturing method is known as a method for directly obtaining a member having a three-dimensional shape.
  • the method is roughly divided into a powder melt laminating method that obtains a shape by locally melting and solidifying a powder (powder bed) formed in advance in layers by irradiation with energy such as a laser or an electron beam, and while spraying the powder.
  • a melt deposition method in which melting and solidification are performed by irradiation of energy, and in any case, a three-dimensional layered object can be formed by melting and solidifying powder.
  • the metal layer formed by melting and solidifying has a molten and solidified structure (rapidly solidified structure).
  • traces can be seen along the scanning direction of a laser or an electron beam. These can be confirmed by observing the surface of the metal layer with a microscope (such as an optical microscope). Therefore, the reactor control rod of the present invention manufactured by the metal additive manufacturing method has, as appearance characteristics, having a melt-solidified structure and a pattern on the surface.
  • FIG. 1 is a schematic cross-sectional view showing an example of a nuclear reactor control rod and a fuel assembly according to the present invention.
  • the control rod 1a according to the present invention has four blade regions 4a to 4d and a tie rod region 5 that supports the four blade regions 4a to 4d.
  • the blade and the tie rod are conventionally separate members and joined by welding or the like, but the control rod 1a according to the present invention is constituted by one member.
  • a region corresponding to a conventional blade member is referred to as a “blade region”, and a region corresponding to a conventional tie rod member is referred to as a “tie rod region”.
  • a handle region is provided at one of the lengthwise ends of the blade regions 4a to 4d and the tie rod region 5 of the control rod 1a.
  • the handle area is an area used for transportation of the control rod 1a. The handle area is described in FIG.
  • the control rod 1a shown in FIG. 1 has a cross-shaped cross section composed of four blade regions 4a to 4d and a tie rod region 5, and includes four channel boxes in which fuel assemblies (not shown) are accommodated. 20 is inserted.
  • the blade regions 4a to 4d are provided with a cylindrical neutron absorber filling hole 3 filled with a neutron absorber.
  • the neutron absorber filling holes 3 are provided only in one blade (blade region 4a) in FIG. 1, but in actuality, the same number is provided in four blades. The number of neutron absorber filling holes 3 is appropriately changed depending on the output of the core and the like.
  • FIG. 2 is a schematic view showing another aspect of the tip of the blade region in FIG.
  • the tip 6a of the blade region 4a has a square (square) shape.
  • the shape of the tip portion may be an arc shape when viewed from above. The arc shape is more preferable because the stress concentration can be relaxed than the square shape.
  • the adjacent blade regions are configured to form a right angle. Since the corner portion (X portion in FIG. 1) formed by the blade regions 4a to 4d and the tie rod region 5 is a portion where corrosion products are easily deposited, it is preferable to round the corner of this portion into an arc shape. .
  • As a method of making the corner portion into an arc shape it is conceivable to form a near net shape structure using a metal additive manufacturing method and to make the corner portion into an arc shape. By using grinder processing or the like after modeling, the corner portion can be accurately formed into an arc shape.
  • FIG. 3 is a schematic cross-sectional view showing another example of a nuclear reactor control rod and a fuel assembly according to the present invention.
  • FIG. 3 shows a structure in which the core structure is denser than the structure shown in FIG.
  • the shape of the cross section of the channel box is hexagonal, and the cross section of the control rod 1 b is set so as to fit between the three hexagonal channel boxes 21.
  • the shape is a Y-shape.
  • the shape control rod 1b having a Y-shaped cross section is inserted between three channel boxes 21 surrounding a fuel assembly in which a plurality of fuel rods 22 are grouped.
  • FIG. 4 is a schematic diagram enlarging one blade region of FIG. Similar to the control rod 1 a shown in FIG. 1, the control rod 1 b is composed of three blade regions 4 having neutron absorber filling holes 3 and a tie rod region 5 in the central portion that supports them. The number of neutron absorber filling holes 3 in each blade region 4 is the same. The number of the neutron absorber filling holes 3 is changed in accordance with the output of the core or the like.
  • the shape of the tip portion 6 of the blade region 4 is a square shape when viewed from above, but as described above, the arc shape as shown in FIG. Is preferred.
  • each adjacent blade region 4 is configured to form 120 degrees. As in the case of FIG. 1, the corners are preferably arcuate because corrosion products are likely to accumulate.
  • the manufacturing method is as described above.
  • FIG. 5 is a cross-sectional view taken along the line AA ′ of FIG.
  • a handle 7 used as a support portion or the like for carrying the control rod 1a is provided at one end (upper end) of each of the blade region 4 and the tie rod region 5 in the longitudinal direction. Is provided.
  • An upper end portion of the control rod 1 a including the handle 7 is a handle area 8.
  • a blade region 4 having a neutron absorber filling hole 3 and a tie rod region 5 are provided below the handle region 8. 2 also has the structure shown in FIG.
  • the control rod 1a is divided into two regions depending on the amount of neutron irradiation in the state inserted in the core. That is, in the inserted state, it is close to the core (near the handle region 8), is away from the core 9 (region where high neutron absorption capability is required) 9 to receive high neutron irradiation, and almost no neutron dose There are no regions (regions that do not require neutron absorption capability) 10.
  • the region 9 is referred to as “high irradiation region 9”, and the region 10 is referred to as “low irradiation region”.
  • the neutron absorber filling hole 3 penetrates from the upper end to the lower end of the blade region 4.
  • the high irradiation region 9 needs to be filled with a neutron absorber, but the low irradiation region 10 does not need to be filled with a neutron absorber. Therefore, the neutron absorber filling hole 3 in the high irradiation region 9 is filled with a conventional neutron absorber, and the neutron absorber filling hole 3 in the low irradiation region 10 is not filled with the neutron absorber, but the high irradiation region.
  • the holder 11 that is not a neutron absorber can also be referred to as a “dummy material”.
  • boron carbide (B 4 C) powder or pellets and hafnium (Hf) rod are suitable.
  • boron carbide is used for the neutron absorber, helium (He) gas is generated by the (n, ⁇ ) reaction, and the internal pressure of the neutron absorber filling hole 3 may increase. Therefore, as the holder 11 provided in the low irradiation region 10, it is preferable to use a structure having a gap so that helium gas generated from the neutron absorbing material can escape to the outside.
  • the end (lower end) 12 opposite to the handle region 8 of the neutron absorber filling hole 3 is an end for sealing the neutron absorber and the holder 11 to the neutron absorber filling hole 3. It is plugged. Since the end plug joint portion is provided in the low irradiation region 10, even if a gap portion and a welded portion are generated in the end plug joint portion, it does not become a starting point of occurrence of IASCC.
  • the upper end of the control rod 1a corresponding to the high irradiation region 9 to the end plug joint is manufactured as an integral structure using a metal additive manufacturing method.
  • control rod 1a it is possible to eliminate gaps and welds that may be the starting point of IASCC generation from areas where the neutron irradiation amount is high and IASCC may be generated, and the control rod has excellent IASCC resistance. Can be provided.
  • the end of the neutron absorber filling hole 3 is end-plug joined and sealed, and then joined to a drive system region 14 having a control rod driving device 13 for driving the control rod 1a.
  • This joining is welded by laser welding, TIG welding, or the like.
  • the drive system region 14 is a region where the amount of neutron irradiation is extremely low, and the occurrence of SCC and IASCC is not a concern even if the weld remains.
  • FIG. 9 is a flowchart showing an example of a method for manufacturing a reactor control rod according to the present invention.
  • the manufacturing method of the control rod 1a according to the present invention is as follows: S1: Modeling of the handle region 8, S2: Modeling of the blade region 4 and the tie rod region 5, S3: Unmelted powder (raw metal powder) Removal, S4: Neutron absorber filling hole and neutron absorber filling hole are filled, S5: Neutron absorber filling hole is sealed, and S6: Control rod drive unit is joined in this order.
  • the handle region 8 is the lower end and the end plug joint 12 is the upper end. Go. That is, the layers are stacked from the upper end to the lower end in FIG.
  • the unmelted powder raw material remaining in the neutron absorber filling hole 3 is removed.
  • a technique such as shot peening or acid cleaning in order to increase the removal rate of the unmelted powder.
  • the material constituting the control rod 1 is not particularly limited, but it is possible to provide a control rod having higher IASCC resistance by using the following alloy having high neutron irradiation resistance. .
  • a preferred alloy composition is 16% to 26% Cr, 8% to 22% Ni, 0.02% to 0.4% O, 0.08% to 0.005% C, and 0% by mass. 0.1-0.002% N, and at least of 0.2-2.8% Zr, 0.4-5.0% Ta and 0.2-2.6% Ti
  • One kind is further contained, and the balance consists of Fe and inevitable impurities.
  • Fe, Cr, and Ni which are the main constituent elements of the matrix, have relatively low reactivity, but the additive elements Zr, Ta, and Ti are other metal elements and impurity elements (oxygen (O ) And the like, and the compound formed by bonding is likely to precipitate.
  • a control rod 1a was prototyped by metal additive manufacturing using an alloy having the above composition.
  • the composition of the fabricated prototype alloy is shown in Table 1 below.
  • FIG. 6 is an electron microscopic observation photograph (SEM (Scanning Electron Microscope) observation photograph) of the prototype manufactured in Example 1. From the observation results, it can be seen that the average crystal grain size of the matrix is refined to 10 ⁇ m or less (about 5 ⁇ m). This is presumably because the crystal grain size is refined by the precipitates dispersed in the matrix. Having such fine crystal grains is a feature resulting from the production by the metal additive manufacturing method.
  • FIG. 7 is a diagram showing an XRD pattern of the precipitate of the prototype, and Table 2 shows the composition of the precipitate. As shown in FIG. 7 and Table 2, the precipitate is found to be an oxide of Zr (ZrO or ZrO 2 ) which is an additive element of the alloy.
  • Table 3 shows the average crystal grain size and maximum crystal grain size of the mother phase of the prototype, and the average grain size and number density of the precipitates.
  • Japanese Laid-Open Patent Publication No. 2002-533736 which is a well-known document, discloses a control rod for a boiling water reactor in which a center and an absorption blade are arranged in a cross shape. Referring to the drawings, a blade, a tie rod, and a handle are disclosed. However, no specific manufacturing method is disclosed. In addition, it is described that a horizontal hole-shaped absorption channel (described in FIG.
  • FIG. 2d discloses a control rod having a vertical hole-like absorption channel as in the present invention, but it is extremely difficult to accurately provide such a vertical hole in the member.
  • a control rod disclosed in JP 2013-88157 A which is another known document, has a blade manufactured as an integral structure by HIP processing.
  • a plurality of long rectangular tubes containing neutron absorbers are arranged, sandwiched between thin plates called cover plates, and diffusion-bonded by HIP processing to produce a blade having a vertical hole.
  • the blades are joined to each other by a blade and a bridge, and the bridge is joined by welding. Therefore, it has the structure which cannot exclude the clearance gap part and the welding part in the bridge
  • Japanese Patent Laid-Open No. 2015-203636 discloses a core component manufactured by a metal lamination method, but is a control rod for a fast breeder reactor and is a subject of the present invention.
  • the configuration is different from that of a control rod for a boiling water reactor having a tie rod and a handle.
  • FIG. 8 is a cross-sectional view of a nuclear reactor control rod according to the second embodiment.
  • FIG. 8 is a cross-sectional view of a portion of the control rod corresponding to the cross-sectional view taken along the line AA ′ in FIG.
  • a difference of the control rod 1c according to the second embodiment from the control rod 1a of the first embodiment is that an opening 15 is provided in the tie rod region 5.
  • the channel box surrounding the control rod is made of a zirconium alloy.
  • the tensile strength and elongation of the zirconium alloy are 410 MPa and 20% or more, respectively, and the channel box made of the flexible zirconium alloy is warped by the shaking of the earthquake.
  • the control rod is inserted into the core along the warp of the channel box while the control rod itself is also warped. Therefore, if the control rod has high rigidity, the warpage of the control rod will be smaller than the warpage of the channel box, causing collision with the channel box, causing damage and breakage, and in the worst case, causing poor insertion. Rise.
  • the control rod 1c according to this embodiment shown in FIG. 8 has an opening 15 in the tie rod region 5.
  • the blade and the tie rod are prepared as separate members and then joined together, it is difficult to make an opening in a portion to be a joining portion of each member.
  • the structure shown in FIG. 8 can be easily manufactured.
  • the opening 15 has a quadrangular shape when the longitudinal cross section of the control rod 1 is viewed.
  • the circular arc shape it is possible to prevent the accumulation of corrosion products at the corners. Since it can do, it is more preferable.
  • Other structures and manufacturing methods are the same as those in the first embodiment.
  • control rod for a nuclear reactor that can eliminate the gap and the welded portion and prevent the SCC Oo IASCC and the method for manufacturing the nuclear reactor control rod having such characteristics are provided. It was demonstrated that can be provided.
  • this invention is not limited to the above-mentioned Example, Various modifications are included.
  • the above-described embodiments have been described in detail for easy understanding of the present invention, and are not necessarily limited to those having all the configurations described.
  • a part of the configuration of a certain embodiment can be replaced with the configuration of another embodiment, and the configuration of another embodiment can be added to the configuration of a certain embodiment.
  • 1a, 1b, 1c ... control rod, 20, 21 ... channel box, 22 ... fuel rod, 3 ... neutron absorber filling hole, 4, 4a-4d ... blade region, 5 ... tie rod region, 6, 6a, 6b ... blade Tip, 7 ... handle, 8 ... handle region, 9 ... high irradiation region, 10 ... low irradiation region, 11 ... holder, 12 ... end plug joint, 13 ... control rod drive device, 14 ... drive system region, 15 ... Aperture.

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  • Engineering & Computer Science (AREA)
  • Physics & Mathematics (AREA)
  • Plasma & Fusion (AREA)
  • General Engineering & Computer Science (AREA)
  • High Energy & Nuclear Physics (AREA)
  • Chemical & Material Sciences (AREA)
  • Chemical Kinetics & Catalysis (AREA)
  • Manufacturing & Machinery (AREA)
  • Monitoring And Testing Of Nuclear Reactors (AREA)

Abstract

L'invention concerne une barre de commande pour un réacteur nucléaire et un procédé de fabrication d'une barre de commande pour un réacteur nucléaire grâce auxquels les vides et les parties soudées sont éliminés, et qui permettent d'éviter la corrosion sous contrainte et la corrosion sous contrainte assistée par irradiation. Cette barre de commande pour un réacteur nucléaire est caractérisée en ce qu'elle est conçue à partir d'un élément comprenant une zone formant lame comportant un trou de remplissage de matériau d'absorption de neutrons, une zone formant tige de liaison qui supporte la zone formant lame et une zone formant poignée disposée à une extrémité dans le sens longitudinal de la zone formant lame et de la zone formant tige de liaison, et en ce que l'élément présente une structure solidifiée à l'état fondu. La barre de commande pour un réacteur nucléaire possédant les caractéristiques mentionnées ci-dessus est fabriquée par un procédé de moulage en couches métalliques.
PCT/JP2017/045029 2017-01-12 2017-12-15 Barre de commande pour réacteur nucléaire et son procédé de fabrication Ceased WO2018131379A1 (fr)

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JP2017003313A JP2020063906A (ja) 2017-01-12 2017-01-12 原子炉用制御棒及びその製造方法
JP2017-003313 2017-01-12

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Cited By (1)

* Cited by examiner, † Cited by third party
Publication number Priority date Publication date Assignee Title
CN118893218A (zh) * 2024-06-28 2024-11-05 东方电气（武汉）核设备有限公司 反应堆堆内构件用多连管连续导向组件的制备方法

Citations (5)

* Cited by examiner, † Cited by third party
Publication number Priority date Publication date Assignee Title
JP2011080985A (ja) * 2009-09-11 2011-04-21 Hitachi-Ge Nuclear Energy Ltd 沸騰水型原子炉用制御棒
JP2013033065A (ja) * 2012-11-05 2013-02-14 Hitachi Ltd 軽水炉の炉心及び軽水炉用燃料集合体
JP2013170863A (ja) * 2012-02-20 2013-09-02 Hitachi-Ge Nuclear Energy Ltd 制御棒
JP2015203636A (ja) * 2014-04-15 2015-11-16 日立Ｇｅニュークリア・エナジー株式会社 核燃料集合体および制御棒
WO2016006280A1 (fr) * 2014-07-07 2016-01-14 株式会社日立製作所 Acier inoxydable austénitique et son procédé de production

Patent Citations (5)

* Cited by examiner, † Cited by third party
Publication number Priority date Publication date Assignee Title
JP2011080985A (ja) * 2009-09-11 2011-04-21 Hitachi-Ge Nuclear Energy Ltd 沸騰水型原子炉用制御棒
JP2013170863A (ja) * 2012-02-20 2013-09-02 Hitachi-Ge Nuclear Energy Ltd 制御棒
JP2013033065A (ja) * 2012-11-05 2013-02-14 Hitachi Ltd 軽水炉の炉心及び軽水炉用燃料集合体
JP2015203636A (ja) * 2014-04-15 2015-11-16 日立Ｇｅニュークリア・エナジー株式会社 核燃料集合体および制御棒
WO2016006280A1 (fr) * 2014-07-07 2016-01-14 株式会社日立製作所 Acier inoxydable austénitique et son procédé de production

Cited By (1)

* Cited by examiner, † Cited by third party
Publication number Priority date Publication date Assignee Title
CN118893218A (zh) * 2024-06-28 2024-11-05 东方电气（武汉）核设备有限公司 反应堆堆内构件用多连管连续导向组件的制备方法

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