CN108701500B - 密封具有由高铬钢制成的套管的核反应堆燃料元件的方法 - Google Patents

密封具有由高铬钢制成的套管的核反应堆燃料元件的方法 Download PDF

Info

Publication number
CN108701500B
CN108701500B CN201680079419.8A CN201680079419A CN108701500B CN 108701500 B CN108701500 B CN 108701500B CN 201680079419 A CN201680079419 A CN 201680079419A CN 108701500 B CN108701500 B CN 108701500B
Authority
CN
China
Prior art keywords
plug
fuel element
welding
casing
ferrite
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.)
Active
Application number
CN201680079419.8A
Other languages
English (en)
Other versions
CN108701500A (zh
Inventor
N·S·格里亚诺夫
O·A·克鲁格洛夫
M·V·列昂特瓦-斯米诺娃
I·A·瑙美科
M·V·斯库波夫
V·P·斯米尔诺夫
Y·V·索罗金
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.)
Russian Federation Represented By Russian Atomic Energy Group
Original Assignee
Russian Federation Represented By Russian Atomic Energy Group
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 Russian Federation Represented By Russian Atomic Energy Group filed Critical Russian Federation Represented By Russian Atomic Energy Group
Publication of CN108701500A publication Critical patent/CN108701500A/zh
Application granted granted Critical
Publication of CN108701500B publication Critical patent/CN108701500B/zh
Active legal-status Critical Current
Anticipated expiration legal-status Critical

Links

Classifications

    • G—PHYSICS
    • G21—NUCLEAR PHYSICS; NUCLEAR ENGINEERING
    • G21C—NUCLEAR REACTORS
    • G21C3/00—Reactor fuel elements and their assemblies; Selection of substances for use as reactor fuel elements
    • G21C3/02—Fuel elements
    • G21C3/04—Constructional details
    • G21C3/06—Casings; Jackets
    • G21C3/07—Casings; Jackets characterised by their material, e.g. alloys
    • 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
    • G21C21/02—Manufacture of fuel elements or breeder elements contained in non-active casings
    • B—PERFORMING OPERATIONS; TRANSPORTING
    • B23—MACHINE TOOLS; METAL-WORKING NOT OTHERWISE PROVIDED FOR
    • B23K—SOLDERING OR UNSOLDERING; WELDING; CLADDING OR PLATING BY SOLDERING OR WELDING; CUTTING BY APPLYING HEAT LOCALLY, e.g. FLAME CUTTING; WORKING BY LASER BEAM
    • B23K33/00—Specially-profiled edge portions of workpieces for making soldering or welding connections; Filling the seams formed thereby
    • B23K33/004—Filling of continuous seams
    • B23K33/006—Filling of continuous seams for cylindrical workpieces
    • B—PERFORMING OPERATIONS; TRANSPORTING
    • B23—MACHINE TOOLS; METAL-WORKING NOT OTHERWISE PROVIDED FOR
    • B23K—SOLDERING OR UNSOLDERING; WELDING; CLADDING OR PLATING BY SOLDERING OR WELDING; CUTTING BY APPLYING HEAT LOCALLY, e.g. FLAME CUTTING; WORKING BY LASER BEAM
    • B23K9/00—Arc welding or cutting
    • B23K9/02—Seam welding; Backing means; Inserts
    • B23K9/028—Seam welding; Backing means; Inserts for curved planar seams
    • B—PERFORMING OPERATIONS; TRANSPORTING
    • B23—MACHINE TOOLS; METAL-WORKING NOT OTHERWISE PROVIDED FOR
    • B23K—SOLDERING OR UNSOLDERING; WELDING; CLADDING OR PLATING BY SOLDERING OR WELDING; CUTTING BY APPLYING HEAT LOCALLY, e.g. FLAME CUTTING; WORKING BY LASER BEAM
    • B23K9/00—Arc welding or cutting
    • B23K9/16—Arc welding or cutting making use of shielding gas
    • B—PERFORMING OPERATIONS; TRANSPORTING
    • B23—MACHINE TOOLS; METAL-WORKING NOT OTHERWISE PROVIDED FOR
    • B23K—SOLDERING OR UNSOLDERING; WELDING; CLADDING OR PLATING BY SOLDERING OR WELDING; CUTTING BY APPLYING HEAT LOCALLY, e.g. FLAME CUTTING; WORKING BY LASER BEAM
    • B23K9/00—Arc welding or cutting
    • B23K9/16—Arc welding or cutting making use of shielding gas
    • B23K9/164—Arc welding or cutting making use of shielding gas making use of a moving fluid
    • B—PERFORMING OPERATIONS; TRANSPORTING
    • B23—MACHINE TOOLS; METAL-WORKING NOT OTHERWISE PROVIDED FOR
    • B23K—SOLDERING OR UNSOLDERING; WELDING; CLADDING OR PLATING BY SOLDERING OR WELDING; CUTTING BY APPLYING HEAT LOCALLY, e.g. FLAME CUTTING; WORKING BY LASER BEAM
    • B23K9/00—Arc welding or cutting
    • B23K9/23—Arc welding or cutting taking account of the properties of the materials to be welded
    • G—PHYSICS
    • G21—NUCLEAR PHYSICS; NUCLEAR ENGINEERING
    • G21C—NUCLEAR REACTORS
    • G21C3/00—Reactor fuel elements and their assemblies; Selection of substances for use as reactor fuel elements
    • G21C3/02—Fuel elements
    • G21C3/04—Constructional details
    • G21C3/06—Casings; Jackets
    • G21C3/10—End closures ; Means for tight mounting therefor
    • B—PERFORMING OPERATIONS; TRANSPORTING
    • B23—MACHINE TOOLS; METAL-WORKING NOT OTHERWISE PROVIDED FOR
    • B23K—SOLDERING OR UNSOLDERING; WELDING; CLADDING OR PLATING BY SOLDERING OR WELDING; CUTTING BY APPLYING HEAT LOCALLY, e.g. FLAME CUTTING; WORKING BY LASER BEAM
    • B23K2101/00—Articles made by soldering, welding or cutting
    • B23K2101/04—Tubular or hollow articles
    • B—PERFORMING OPERATIONS; TRANSPORTING
    • B23—MACHINE TOOLS; METAL-WORKING NOT OTHERWISE PROVIDED FOR
    • B23K—SOLDERING OR UNSOLDERING; WELDING; CLADDING OR PLATING BY SOLDERING OR WELDING; CUTTING BY APPLYING HEAT LOCALLY, e.g. FLAME CUTTING; WORKING BY LASER BEAM
    • B23K2101/00—Articles made by soldering, welding or cutting
    • B23K2101/04—Tubular or hollow articles
    • B23K2101/06—Tubes
    • B—PERFORMING OPERATIONS; TRANSPORTING
    • B23—MACHINE TOOLS; METAL-WORKING NOT OTHERWISE PROVIDED FOR
    • B23K—SOLDERING OR UNSOLDERING; WELDING; CLADDING OR PLATING BY SOLDERING OR WELDING; CUTTING BY APPLYING HEAT LOCALLY, e.g. FLAME CUTTING; WORKING BY LASER BEAM
    • B23K2101/00—Articles made by soldering, welding or cutting
    • B23K2101/04—Tubular or hollow articles
    • B23K2101/14—Heat exchangers
    • B—PERFORMING OPERATIONS; TRANSPORTING
    • B23—MACHINE TOOLS; METAL-WORKING NOT OTHERWISE PROVIDED FOR
    • B23K—SOLDERING OR UNSOLDERING; WELDING; CLADDING OR PLATING BY SOLDERING OR WELDING; CUTTING BY APPLYING HEAT LOCALLY, e.g. FLAME CUTTING; WORKING BY LASER BEAM
    • B23K2103/00—Materials to be soldered, welded or cut
    • B23K2103/02—Iron or ferrous alloys
    • B23K2103/04—Steel or steel alloys
    • B—PERFORMING OPERATIONS; TRANSPORTING
    • B23—MACHINE TOOLS; METAL-WORKING NOT OTHERWISE PROVIDED FOR
    • B23K—SOLDERING OR UNSOLDERING; WELDING; CLADDING OR PLATING BY SOLDERING OR WELDING; CUTTING BY APPLYING HEAT LOCALLY, e.g. FLAME CUTTING; WORKING BY LASER BEAM
    • B23K2103/00—Materials to be soldered, welded or cut
    • B23K2103/02—Iron or ferrous alloys
    • B23K2103/04—Steel or steel alloys
    • B23K2103/05—Stainless steel
    • 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

Landscapes

  • Engineering & Computer Science (AREA)
  • Physics & Mathematics (AREA)
  • Plasma & Fusion (AREA)
  • General Engineering & Computer Science (AREA)
  • High Energy & Nuclear Physics (AREA)
  • Mechanical Engineering (AREA)
  • Manufacturing & Machinery (AREA)
  • Metallurgy (AREA)
  • Chemical & Material Sciences (AREA)
  • Materials Engineering (AREA)
  • Butt Welding And Welding Of Specific Article (AREA)
  • Arc Welding In General (AREA)

Abstract

本发明涉及核能并且可以用于制造核反应堆的燃料元件。提出了一种密封核反应堆燃料元件的方法，所述方法包括将高铬钢套管的一端焊接到高铬钢塞、给燃料元件加载燃料、以及将第二塞焊接到套管的另一端。套管为高铬铁素体‑马氏体钢且塞为高铬铁素体钢。以促进焊缝金属形成而允许在所述金属中形成铁素体相的套管和塞的材料的体积比进行氩弧焊，其中所述比例为：V1/V2≥0.18，其中V1是铁素体材料的体积且V2是铁素体‑马氏体材料的体积。在14‑20A电流、12‑15米/小时速度、9‑10W电弧电压和7‑8升/分钟氩气流速下进行氩弧焊。该方法提供了期望的焊接接头质量并简化了燃料元件的制造工艺。

Description

密封具有由高铬钢制成的套管的核反应堆燃料元件的方法
本发明涉及核能，并且可以用于制造动力反应堆的燃料元件。
存在一种用于密封燃料元件的已知方法，其中通过在保护气体的气氛中使用非自耗性电极将套管端部与塞一起熔化来进行焊接(美国专利3045108)。
该方法的缺点在于，电极和塞的圆柱形凸起之间的接触引发电弧，使得钨夹杂物进入焊池，这会降低强度，并相应地降低焊接接头的质量。
另一种通过熔焊密封燃料元件的已知方法包括将由与燃料元件套管相同的材料制成的塞焊接到由1Х18Н10Т(1Cr18Ni10Тi)不锈钢制成的套管的一端；加载燃料，然后将第二塞焊接到套管的另一端，从而紧密密封容纳燃料的燃料元件(参见书：作者AGSamoylov、VS Volkov、MI Solonin，“核反应堆的燃料元件”，Moscow，Atomenergoizdat，1996年，类似方法)。该方法公开了密封燃料元件所需的所有必要技术操作，其中使用振荡器来引发电弧。
近年来，鉴于更高的快中子反应堆燃料元件性能特性标准(如辐射剂量、冷却剂腐蚀-侵蚀效应和温度)，使用以下等级的高铬铁素体-马氏体钢来制造燃料元件套管：ЭИ-852(13Cr13Si2Mo2)、ЭИ-823(16Cr12MoWSiVNbB)、ЭИ-900(16Cr12SiMoWVNbNB)。
最接近的类似方法是用高铬钢制成的套管密封燃料元件的方法，其包括将由与燃料元件套管相同的材料制成的塞焊接到套管的一端，加载燃料，然后将第二塞焊接至套管的另一端形成焊接接头组件，最后对焊接接头进行回火以除去其中的淬火结构(参见由Ph.G.Reshetnikov编辑的“动力反应堆燃料元件的开发、生产和操作”，第2卷，Energatomizdat，1995г，原型)。
这种焊接该等级钢的方法的主要缺点是在这些钢中完成焊接一段时间后形成淬火结构和冷裂纹的趋势。
该方法的缺点是需要额外的操作来生产这种钢的高质量焊接接头，特别是焊接接头回火，其在740-760℃下进行20-30分钟，并且将焊接操作和随后的回火之间的时间保持得尽可能短。在回火焊缝之后进行的这种操作成本高，并且增加了燃料元件制造技术的复杂性，特别是在对密封装载有燃料的燃料元件的焊接接头进行回火时如此。
本发明的技术效果是通过在套管和塞之间提供高质量的焊接接头来增加具有高铬钢套管的核反应堆燃料元件的密封耐久性，而无需随后对焊缝进行后续热处理，从而简化了制造工艺。
该技术效果由密封核反应堆燃料元件的方法提供的，所述方法包括将高铬钢套管的一端焊接到高铬钢塞、给燃料元件加载燃料、以及将第二塞焊接到套管的另一端，其中套管为高铬铁素体-马氏体钢且塞为高铬铁素体钢，其中以促进焊缝金属形成而允许在所述金属中形成铁素体相的所述套管和所述塞的材料的体积比进行氩弧焊，其中所述比例为：
V1/V2≥0.18,
其中：V1是铁素体材料的体积；
V2是铁素体-马氏体材料的体积。
在14-20A电流、12-15米/小时速度、9-10W电弧电压和7-8升/分钟氩气流速下进行氩弧焊。
焊接接头金属中铁素体和铁素体-马氏体材料的体积比≥0.18，其基于如下事实：在接合熔融区中以大于或等于指定值的值形成稳定的铁素体相，并且铁素体相不易冷裂且不需要对焊接接头进行回火；在较低的值下，不会形成所需的铁素体相，使得必须对焊接接头金属进行热处理。
附图示出了焊接接头组件的结构，其包括由铁素体-马氏体钢构成的套管1和由铁素体钢构成的塞2。
实施例
密封核反应堆燃料元件的方法包括将由高铬钢构成的套管的一端焊接至由高铬钢构成的塞、给燃料元件加载燃料、以及将第二塞焊接到套管的另一端。
在焊接前和焊接后焊接接头组件的几何平面模型上对不同工艺变量如肩宽a、套管厚度δ和预定穿透深度b进行焊接过程建模，然后通过结构分析确定在焊接接头中形成的相，从而允许计算参与形成接合金属的各种等级的钢的面积比，以在其中获得铁素体相。
在考虑其在所形成的接合金属中的比例的情况下，在焊接接头的切片中借助于计算机程序JpSquare(LProSoft)确定了所得到各种等级材料的表面积，并且通过结构分析确定在焊接接头金属中形成的相。在接合金属中形成的相的体积与焊接接头组件的几何平面模型中的金属面积成正比。在接头金属中形成铁素体相所需的套管和塞的材料体积比基于所计算的待耦接材料的面积来确定。
V1/V2≥0.18，
其中：V1是铁素体材料的体积；
V2是铁素体-马氏体材料的体积。
密封方法是使用由ЭИ-823(16Cr12MoWSiVNbB)级铁素体-马氏体钢制成的套管通过氩弧焊来进行的，所述套管的直径为9.3毫米，壁厚为0.5毫米。
使用05Х18С2ВФАЮ(05Cr18Si2WVNAl)级铁素体钢作为塞，其肩宽为0.8毫米，其直径对应于套管直径(参见附图)。
用于焊接的钢的化学成分在表1中示出。
表1-焊接材料的化学组成。
钢的机械特性在表2中示出。
表2-焊接材料的机械特性
使用钢05Х18С2МВФАЮ(05Cr18Si2МoWVNАl)进行的实验证明其在铅冷却剂中具有高机械性能和全面的耐腐蚀性(RU专利2238345，“用于铅冷却剂核反应堆的核心燃料元件的钢”/Velyuhanov V.P.、Zelenskiy G.K.、Ioltuhovskiy A.G.、Leontieva-Smirnova M.V.、Mitin V.S.、Sokolov N.B.、Rusanov A.E.、Troyanov V.M.；申请人和专利持有人-俄罗斯联邦代表联邦原子能机构，SSC VNIINM.；20.10.2004出版)。
用由钢05Х18С2МВФАЮ(05Cr18Si2МoWVNАl)制成的塞焊接由ЭИ-823(16Cr12MoWSiVNbB)钢制成的套管的方式如下：
焊接电流15A，
焊接速度14米/小时，
电弧电压9V，
氩气速率8升/分钟。
采用上述技术制造了燃料元件模拟器。
对于所选焊接方式的焊接接头的金相研究表明，铁素体相与铁素体-马氏体相的体积比为0.46至0.51。
机械强度测试表明，在燃料元件模拟器的套管上出现样品破裂。套管的强度极限为818MPa。
在铅冷却剂中对焊接接头进行4000小时的腐蚀测试。已经发现，焊接接头的耐腐蚀性保持在燃料套管的耐腐蚀性水平。
在室温下通过质谱法利用氦气泄漏检测器进行的气密性焊接接头的测试表明所有接头都是气密密封的。
使用本发明的密封具有由高铬钢制成的套管的燃料元件的方法允许改善套管和插塞之间的焊接接头的质量并且大幅简化了密封技术。

Claims (2)

1.一种密封核反应堆燃料元件的方法，所述方法包括将由高铬钢构成的套管的一端焊接到由高铬钢制成的塞、给所述燃料元件加载燃料、以及将第二塞焊接到所述套管的另一端，其特征在于所述套管由高铬铁素体-马氏体钢构成且所述塞由高铬铁素体钢构成，对具有一定体积比例的形成焊缝金属的所述套管材料和所述塞材料进行氩弧焊，使得在所述焊缝金属中形成铁素体相，其中所述比例为：
V1/V2≥0.18,
其中：V1是铁素体材料的体积；
V2是铁素体-马氏体材料的体积。
2.根据权利要求1所述的方法，其特征在于在14-20A焊接电流、12-15米/小时焊接速度、9-10V电弧电压和7-8升/分钟氩气流速下进行氩弧焊。
CN201680079419.8A 2015-11-26 2016-11-23 密封具有由高铬钢制成的套管的核反应堆燃料元件的方法 Active CN108701500B (zh)

Applications Claiming Priority (3)

Application Number Priority Date Filing Date Title
RU2015150743/07A RU2603355C1 (ru) 2015-11-26 2015-11-26 Способ герметизации тепловыделяющих элементов ядерного реактора с оболочкой из высокохромистой стали
RU2015150743 2015-11-26
PCT/RU2016/000808 WO2017091111A1 (ru) 2015-11-26 2016-11-23 Способ герметизации тепловыделяющих элементов ядерного реактора с оболочкой из высокохромистой стали

Publications (2)

Publication Number Publication Date
CN108701500A CN108701500A (zh) 2018-10-23
CN108701500B true CN108701500B (zh) 2019-11-26

Family

ID=57774487

Family Applications (1)

Application Number Title Priority Date Filing Date
CN201680079419.8A Active CN108701500B (zh) 2015-11-26 2016-11-23 密封具有由高铬钢制成的套管的核反应堆燃料元件的方法

Country Status (7)

Country Link
US (1) US10580537B2 (zh)
EP (1) EP3382717B1 (zh)
JP (1) JP6556357B2 (zh)
KR (1) KR102065868B1 (zh)
CN (1) CN108701500B (zh)
RU (1) RU2603355C1 (zh)
WO (1) WO2017091111A1 (zh)

Families Citing this family (3)

* Cited by examiner, † Cited by third party
Publication number Priority date Publication date Assignee Title
CN110253111A (zh) * 2019-07-12 2019-09-20 中船桂江造船有限公司 一种1cr18ni钢板+铝铝钢复合材料焊接方法
CN110253109B (zh) * 2019-07-12 2022-11-15 中船桂江造船有限公司 一种CCSB钢+1Cr18NI9TI异种钢的焊接方法
RU2760492C1 (ru) * 2020-12-31 2021-11-25 Акционерное общество «Научно-технический центр «Диапром» Тепловыделяющий элемент ядерного реактора

Citations (4)

* Cited by examiner, † Cited by third party
Publication number Priority date Publication date Assignee Title
US3045108A (en) * 1961-01-24 1962-07-17 Cecil C Stone Fuel container closure
GB2258419A (en) * 1991-08-05 1993-02-10 Westinghouse Electric Corp Fuel rod end plug welding method and end face trepan configuration
JPH06160589A (ja) * 1992-11-20 1994-06-07 Mitsubishi Nuclear Fuel Co Ltd 燃料棒の加圧溶接方法
RU2302044C1 (ru) * 2005-10-10 2007-06-27 Российская Федерация в лице Федерального агентства по атомной энергии Твэл реактора на быстрых нейтронах со свинцовым теплоносителем (варианты)

Family Cites Families (14)

* Cited by examiner, † Cited by third party
Publication number Priority date Publication date Assignee Title
US3460236A (en) * 1967-04-20 1969-08-12 Atomic Power Dev Ass Inc Method of making nuclear reactor fuel elements
US3836431A (en) * 1971-05-04 1974-09-17 Belgonucleaire Sa Nuclear fuel rods having end plugs with bores therethrough sealed by frangible membranes
US4865804A (en) * 1984-05-02 1989-09-12 Westinghouse Electric Corp. Fuel rod end plug
SU1345917A1 (ru) * 1985-05-28 1996-09-27 Р.Х. Гибадуллин Тепловыделяющий элемент ядерного энергетического реактора на быстрых нейтронах
JPH05180986A (ja) * 1991-12-18 1993-07-23 Mitsubishi Nuclear Fuel Co Ltd 燃料棒の製造方法及びそれに用いる端栓
JP4097775B2 (ja) * 1998-04-27 2008-06-11 三菱原子燃料株式会社 燃料棒の溶接方法
KR100387595B1 (ko) * 1999-12-28 2003-06-18 주식회사 포스코 고탄소 마르텐사이트계 스테인리스강의 레이저 용접방법
US20030016777A1 (en) * 2001-07-18 2003-01-23 Alain Vandergheynst TIG welded MOX fuel rod
RU2262753C2 (ru) * 2003-10-06 2005-10-20 Российская Федерация, от имени которой выступает Министерство Российской Федерации по атомной энергии Твэл реактора на быстрых нейтронах (варианты) и оболочка для его изготовления
KR101573511B1 (ko) 2011-03-29 2015-12-01 닛폰 스틸 앤드 스미킨 스테인레스 스틸 코포레이션 용접부의 내식성 및 강도가 우수한 페라이트계 스테인리스강 및 tig 용접 구조물
SE535767C2 (sv) * 2011-04-28 2012-12-11 Westinghouse Electric Sweden Förfarande för svetsning av kärnbränslestav
FR2980804B1 (fr) * 2011-09-30 2014-06-27 Areva Np Procede de realisation a partir d'une ebauche en acier inoxydable austenitique a faible teneur en carbone d'une gaine resistant a l'usure et a la corrosion pour reacteur nucleaire, gaine et grappe de commande correspondantes
US9303295B2 (en) * 2012-12-28 2016-04-05 Terrapower, Llc Iron-based composition for fuel element
US9847143B2 (en) * 2014-04-29 2017-12-19 Westinghouse Electric Company Llc Nuclear fuel element

Patent Citations (4)

* Cited by examiner, † Cited by third party
Publication number Priority date Publication date Assignee Title
US3045108A (en) * 1961-01-24 1962-07-17 Cecil C Stone Fuel container closure
GB2258419A (en) * 1991-08-05 1993-02-10 Westinghouse Electric Corp Fuel rod end plug welding method and end face trepan configuration
JPH06160589A (ja) * 1992-11-20 1994-06-07 Mitsubishi Nuclear Fuel Co Ltd 燃料棒の加圧溶接方法
RU2302044C1 (ru) * 2005-10-10 2007-06-27 Российская Федерация в лице Федерального агентства по атомной энергии Твэл реактора на быстрых нейтронах со свинцовым теплоносителем (варианты)

Also Published As

Publication number Publication date
KR20180113980A (ko) 2018-10-17
RU2603355C1 (ru) 2016-11-27
US10580537B2 (en) 2020-03-03
US20190019586A1 (en) 2019-01-17
JP6556357B2 (ja) 2019-08-07
KR102065868B1 (ko) 2020-01-13
EP3382717B1 (en) 2020-08-19
EP3382717A4 (en) 2019-07-31
JP2019506589A (ja) 2019-03-07
EP3382717A1 (en) 2018-10-03
CN108701500A (zh) 2018-10-23
WO2017091111A1 (ru) 2017-06-01

Similar Documents

Publication Publication Date Title
CN108701500B (zh) 密封具有由高铬钢制成的套管的核反应堆燃料元件的方法
CN108796364B (zh) 一种适用低温的x80大口径厚壁直缝埋弧焊管及其制造方法
CN108778611B (zh) 燃料元件套管和塞之间的焊接接头
Kong et al. Stress corrosion of X80 pipeline steel welded joints by slow strain test in NACE H2S solutions
BR102013021664A2 (pt) Processo para produção de tubo cladeado por trefilação e tubo cladeado
CN102962562A (zh) 一种双相不锈钢焊接接头铁素体控制方法
Wang et al. Effects of multi-pulse tempering on resistance spot welding of DP590 steel
CN109865955A (zh) G115大口径管手工钨极氩弧焊和焊条电弧焊结合的焊接方法
Ju et al. Study of in-situ formation of Fe-Mn-Si shape memory alloy welding seam by laser welding with filler powder
CN107020440A (zh) 一种带有人工焊接裂纹缺陷试板的制作方法
Klobčar et al. Active flux tungsten inert gas welding of austenitic stainless steel AISI 304
CN101670477B (zh) 抗硫化氢井下隔热油管的焊接方法
CN105499769B (zh) 一种适用于抗硫工艺管道焊接的埋弧自动焊焊接工艺
CN103817425A (zh) 金属小构件在氢氮混合气体保护下的银焊接工艺
CN102941399B (zh) 珠光体耐热钢结构件气保护焊接方法
Yang et al. Welding Numerical Simulation Analysis of AP 1000 Insert Plate and Penetration Sleeves Based on ABAQUS
Mansouri et al. Vickers Hardness Test of Steel Pipes Welded by High Frequency Induction
CN110434425B (zh) 一种s60mc柴油机气缸盖燃油喷射区域堆焊方法
Ingle et al. Thermo-mechanical analysis in TIG welding of aluminum alloy 6082
Mendes et al. Increasing the corrosion resistance in the UNS S32750 super duplex steel welded joints through Hybrid GTAW-Laser Welding and Nitrogen
LOBANOV et al. ELIMINATION OF LOCAL DEFORMATIONS OF BUCKLING TYPE BY MEANS OF ELECTRODYNAMIC TREATMENT
CN116833521A (zh) 一种镍基合金625-x65复合管的焊接方法
Mazel' 10٪ Cr–10٪ Ni martensitic welding wires with a low temperature of the γ→ α transformation
Li et al. Research on Coiled Tubing Butt Welding Process
Douty et al. Surfacing of 304 stainless steel for liquid sodium service

Legal Events

Date Code Title Description
PB01 Publication
PB01 Publication
SE01 Entry into force of request for substantive examination
SE01 Entry into force of request for substantive examination
GR01 Patent grant
GR01 Patent grant