–
Development of joining technology between FeCrAl alloys and fusion reactor piping materials
KANAI Ryui, NAOKO Oono, INAO Daisuke, NAGASAKA Takuya, HOKAMOTO Kazuyuki
download PDFAbstract. The use of FeCrAl alloys as an inner lining for piping materials for fusion reactors is being considered. The FeCrAl alloy/SUS316L joints were explosion welded to avoid the influence of an oxide film at the joint interface. The joint length could be increased by increasing the charge ratio or reducing the material thickness. Together with the microstructure observation, hardness test, 4-point bending test and heat treatment test results, it is clear that explosion welding is suitable for joining FeCrAl-ODS and SUS316L.
Keywords
Clad Materials, Intermediate Products, Bonding Distance
Published online 9/15/2024, 7 pages
Copyright © 2024 by the author(s)
Published under license by Materials Research Forum LLC., Millersville PA, USA
Citation: KANAI Ryui, NAOKO Oono, INAO Daisuke, NAGASAKA Takuya, HOKAMOTO Kazuyuki, Development of joining technology between FeCrAl alloys and fusion reactor piping materials, Materials Research Proceedings, Vol. 44, pp 691-697, 2024
DOI: https://doi.org/10.21741/9781644903254-74
The article was published as article 74 of the book Metal Forming 2024
Content from this work may be used under the terms of the Creative Commons Attribution 3.0 license. Any further distribution of this work must maintain attribution to the author(s) and the title of the work, journal citation and DOI.
References
[1] M. Kondo, S. Hatakeyama, N. Oono, T. Nozawa, Corrosion-resistant materials for liquid LiPb fusion blanket in elevated temperature operation, Corros. Sci. 197 (2022) 110070. https://doi.org/10.1016/j.corsci.2021.110070
[2] T. Tanaka, T. Chikada, T. Hinoki, T. Muroga, Electrical insulation performances of ceramic materials developed for advanced blanket systems under intense radiations, J. Nucl. Mater. 569 (2022) 153917. https://doi.org/10.1016/j.jnucmat.2022.153917
[3] M.S. Burton, Metallurgical Principles of Metal Bonding, Welding-J 11 (1954) 1051.
[4] R. Nishio, T. Tanaka, N. Oono, M. Kondo, Reduction of MHD pressure drop by electrical insulating oxide layers in liquid breeder blanket of fusion reactors, Nucl. Mater. Energy 34 (2023) 101382. https://doi.org/10.1016/j.nme.2023.101382
[5] T. Fujio, Explosion Welding, Japan Weld. Soc. 41 (1972) 28-33.
[6] https://www.toyo-success.co.jp/product/characteristic_s.html
[7] https://www.kanthal.com/en/products/material-datasheets/tube/kanthal-apmt/
[8] S. Ukai, K. Sakamoto, S. Ohtsuka, S. Yamashita, A. Kimura, Alloy design and characterization of a recrystallized FeCrAl-ODS cladding for accident-tolerant BWR fuels: An overview of research activity in Japan, J. Nuclear Mater. 583 (2023) 154508. https://doi.org/10.1016/j.jnucmat.2023.154508
[9] Y. Ma, T. Wang, G. Wang, X. Fang, C. Chu, Numerical and experimental studies of the interface characteristics and wave formation mechanism of Hastelloy/stainless steel explosive welding composite plate, Mater. Today Commun. 36 (2023) 106880. https://doi.org/10.1016/j.mtcomm.2023.106880
[10] P. Dou, Z.-X. Xin, W. Sang, A. Kimura, Age-hardening mechanisms of 15Cr ODS ferritic steels with 5, 7 and 9 wt.% Al at 475°C for 9000 h, J. Nucl. Mater. 540 (2020) 152368. https://doi.org/10.1016/j.jnucmat.2020.152368
[11] H. Fu, T. Nagasaka, T. Muroga, W. Guan, S. Nogami, H. Serizawa, S. Geng, K. Yabuuchi, A. Kimura, Plastic deformation behavior and bonding strength of an EBW joint between 9Cr-ODS and JLF-1 estimated by symmetric four-point bend tests combined with FEM analysis, Fusion Eng. Des. 102 (2016) 88-93. https://doi.org/10.1016/j.fusengdes.2015.11.037
[12] https://www.silicolloy.co.jp/characteristic/mechanical2/
