High-Temperature Creep and Microstructure Evolution of Alloy 800H Weldments with Inconel 625 and Haynes 230 Filler Materials

被引:2
作者
Li, Wenjing [1 ]
Xiao, Lin [1 ]
Walters, Lori [1 ]
Dong, Qingshan [1 ]
Ienzi, Maurizio [1 ]
Sloan, Robyn [1 ]
机构
[1] Canadian Nucl Labs, Chalk River, ON K0J 1J0, Canada
来源
APPLIED SCIENCES-BASEL | 2024年 / 14卷 / 04期
关键词
Alloy; 800H; Inconel; 625; Haynes; 230; creep; microstructure; weldment;
D O I
10.3390/app14041347
中图分类号
O6 [化学];
学科分类号
0703 ;
摘要
Alloy 800H stands as one of the few code-qualified materials for fabricating in-core and out-of-core components operating in high-temperature reactors. Welding is a common practice for assembling these components; however, the selection of a suitable filler material is essential for enhancing the high-temperature creep resistance of Alloy 800H weldments in high-temperature applications. In this study, Inconel 625 and Haynes 230 filler materials were used to weld Alloy 800H plates by employing the gas tungsten arc welding technique. The high-temperature tensile and creep rupture properties, microstructural stability, and evolution of the weldments after high-temperature exposure were investigated and compared with those of Alloy 800H. The results show that both weldments exhibit enhanced tensile and creep behavior at 760 degrees C. The creep rupture times of the weldments with Inconel 625 filler and Haynes 230 filler materials were about two and three time longer, respectively, than those of Alloy 800H base metal when tested at 80 MPa and 760 degrees C. Carbides (MC and M23C6) were commonly observed in the microstructures of both the weld and base metals in the two weldments after high-temperature creep tests. However, the Inconel 625 filler weldment displayed detrimental delta and Laves phases in the fusion zone, and these precipitates could be potential sites for initiating cracks following prolonged high-temperature exposure. This study shows that the weldment with Haynes 230 filler material exhibit better phase stability and creep rupture properties than the one with Inconel 625, suggesting its potential for use as a candidate filler material for Alloy 800H for further investigation. This finding also emphasizes the critical consideration of microstructural evolutions and phase stability in evaluating high-temperature materials and their weldments in high-temperature reactor applications.
引用
收藏
页数:20
相关论文
共 25 条
  • [1] [Anonymous], 2018, ASTM E139-11
  • [2] [Anonymous], 2019, Rules for Construction of Nuclear Facility Components, Division 5 High Temperature Reactors
  • [3] Abnormal Strain Rate Sensitivity Driven by a Unit Dislocation-Obstacle Interaction in bcc Fe
    Bai, Zhitong
    Fan, Yue
    [J]. PHYSICAL REVIEW LETTERS, 2018, 120 (12)
  • [4] A Deformation Mechanism Map for Incoloy 800H Optimized Using the Genetic Algorithm
    Beardsley, Aaron L.
    Bishop, Catherine M.
    Kral, Milo V.
    [J]. METALLURGICAL AND MATERIALS TRANSACTIONS A-PHYSICAL METALLURGY AND MATERIALS SCIENCE, 2019, 50A (09): : 4098 - 4110
  • [5] Booker M.K., 1983, Analysis of the Creep Strain-Time Behaviour of Alloy 800, ORNL/TM-8449
  • [6] Callister W.D., 1999, Materials Science and Engineering: An Introduction
  • [7] Melting and solidification study of Alloy 625
    Cieslak, M.J.
    Headley, T.J.
    Kollie, T.
    Romig Jr., A.D.
    [J]. Metallurgical transactions. A, Physical metallurgy and materials science, 1988, 19 A (09): : 2319 - 2331
  • [8] Solidification of Nb-bearing superalloys: Part II. Pseudoternary solidification surfaces
    DuPont, JN
    Robino, CV
    Marder, AR
    Notis, MR
    [J]. METALLURGICAL AND MATERIALS TRANSACTIONS A-PHYSICAL METALLURGY AND MATERIALS SCIENCE, 1998, 29 (11): : 2797 - 2806
  • [9] Floreen S., The Metallurgy of Alloy 625, DOI DOI 10.7449/1994/SUPERALLOYS_1994_13_37.PDF
  • [10] Considerations of Material Selection for Control Rod Drive Mechanism of Reaktor Daya Eksperimental
    Hastuty, Sri
    Zacharias, Petrus
    Awwaluddin, M.
    Krismawan
    Setiawan, Putut Hery
    Siswanto, Edy
    Santoso, Budi
    Nugroho, Ari
    Abdul-Rani, Ahmad Majdi
    [J]. SYMPOSIUM OF EMERGING NUCLEAR TECHNOLOGY AND ENGINEERING NOVELTY (SENTEN 2018), 2019, 1198