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    • 1. 发明申请
    • Welding process for stainless steel piping
    • 不锈钢管道焊接工艺
    • US20060201915A1
    • 2006-09-14
    • US11354910
    • 2006-02-16
    • Takeshi ObanaShoji ImanagaEiji AshidaXiangjun LuoHiroo KoideMitsuaki Haneda
    • Takeshi ObanaShoji ImanagaEiji AshidaXiangjun LuoHiroo KoideMitsuaki Haneda
    • B23K9/04
    • B23K9/0213B23K2101/06B23K2103/05
    • The present invention has an object to reduce residual stress in a tensile direction of a weld on the inner side in contact with reactor water of austenitic stainless steel piping, and to change the residual stress into compressive stress, to reduce stress corrosive cracking. The present invention provides a welding process for stainless steel piping of laminating two types of welding wire made of different materials in a groove of austenitic stainless steel piping, including at least one of a first layer penetration welding step of performing a predetermined back bead width on the back side of the groove bottom and a tack welding step, a first lamination welding step of lamination welding of austenitic stainless steel wire from the bottom to the top of the groove, and a second lamination welding step of lamination welding of nickel-base alloy wire to a final layer at the top of the groove.
    • 本发明的目的是减少与奥氏体不锈钢管道的反应器水接触的内侧的焊缝的拉伸方向的残余应力,并且将残余应力变为压缩应力,以减少应力腐蚀开裂。 本发明提供一种用于在奥氏体不锈钢管道的槽中层叠由不同材料制成的两种类型的焊丝的不锈钢管道的焊接工艺,其包括以下步骤中的至少一个:执行预定的后焊道宽度的第一层穿透焊接步骤 凹槽底部的背面和定位焊接步骤,从底部到顶部的奥氏体不锈钢丝层压焊接的第一层压焊接步骤,以及镍基合金的层压焊接的第二层压焊接步骤 导线到槽顶部的最后层。
    • 4. 发明授权
    • Method for weld repairing of structures in nuclear reactors
    • 核反应堆结构焊缝修复方法
    • US5674419A
    • 1997-10-07
    • US498485
    • 1995-07-05
    • Hiroo KoideYasumasa TamaiJunichiro MorisawaToshimi MatsumotoKeiichi Uraki
    • Hiroo KoideYasumasa TamaiJunichiro MorisawaToshimi MatsumotoKeiichi Uraki
    • G21C19/02B23K9/00B23K9/04B23K31/02
    • B23K31/02
    • Disclosed is a highly reliable weld repairing method to repair a crack defect in structures and apparatus inside pressure vessels of nuclear reactors, while preventing generation of new crack defects in the structures and apparatus during the repairing. These structures and apparatus are made of any of stainless steel and Ni-base alloys, and are irradiated with high energy corpuscular ray during operating period of the reactor. The repairing method includes the steps of eliminating a region of the structure or the apparatus including a portion having the crack defect, and executing spot welding at a surface of the region continuously or interruptedly in a manner so as to form a first welded layer in a manner that each of the spot welded spots is half-overlapped with adjacent welded spots. Additionally, welding for forming at least a second layer, on the first welded layer, so that the at least a second layer is not deeper than a weld penetration thickness of the first welded layer can be performed.
    • 公开了一种高度可靠的焊接修复方法,用于修复核反应堆压力容器内的结构和设备中的裂纹缺陷,同时防止在修复期间在结构和设备中产生新的裂纹缺陷。 这些结构和装置由不锈钢和镍基合金中的任何一种制成,并且在反应器运行期间被照射高能量红外线。 修复方法包括以下步骤:消除结构的区域或包括具有裂纹缺陷的部分的设备,并且以连续或间断的方式在该区域的表面上进行点焊以形成第一焊接层 每个点焊点与相邻焊接点半重叠的方式。 此外,可以进行在第一焊接层上形成至少第二层的至少第二层的焊接,使得至少第二层不比第一焊接层的焊接穿透厚度更深。