Abstract
An oxide-dispersion-strengthened FeCrAl (FeCrAl-ODS) has been continuously developed in Japan as a promising candidate alloy for the accident tolerant fuel cladding of BWRs (boiling water reactors). This paper will introduce the progress in practical development of accident tolerant FeCrAl-ODS fuel claddings for BWRs in the program fully or partially supported and organized by the Ministry of Economy, Trade and Industry (METI) of Japan.
The experimental studies have been conducted to obtain and accumulate key material properties of FeCrAl-ODS fuel claddings to support the evaluations in the analytical studies. For the evaluation at normal operation condition, fatigue test of unirradiated fuel cladding and tensile test of irradiated sheet specimen were conducted. In the fatigue test, a tensile-compressive bending strain was loaded on the C-shaped specimens by cyclic movement of a push-pull rod. Test temperature was 623 K, frequency was 1 Hz, and strain amplitude were 0.27, 0.34 and 0.55%. The results of fatigue tests demonstrated that cycles to failure of the FeCrAl-ODS cladding were higher than that of the O’Donnell and Langer fatigue curve of Zr-based alloy. The tensile test was conducted in a hot cell using the SS-J2 type specimens at ambient temperature, 573 K and 623 K at a strain rate of 10–3 s−1. The specimens were irradiated up to 7.8 and 13 dpa at 573 K in the High Flux Isotope Reactor at ORNL. The irradiation hardening and ductility loss obtained at 7.8 and 13 dpa were comparable to those at 3.9 dpa.
Access this chapter
Tax calculation will be finalised at checkout
Purchases are for personal use only
Similar content being viewed by others
References
TEPCO, The development of and lessons from the Fukushima Daiichi nuclear accident, https://www.tepco.co.jp/en/decommision/accident/images/outline01.pdf.
OECD/NEA, State-of-the-art report on light water reactor accident-tolerant fuels, NEA No. 7317 (2018).
K. Terrani, Accident tolerant fuel cladding development: Promise, status, and challenges, J. Nucl. Mater., 501 (2018) 13–30.
K. Sakamoto, Y. Miura, S. Ukai, N.H. Oono, A. Kimura, A. Yamaji, K. Kusagaya, S. Takano, T. Kondo, T. Ikegawa, I. Ioka, S. Yamashita, Development of accident tolerant FeCrAl-ODS fuel cladding for BWRs in Japan, J. Nucl. Mater., 557 (2021) 153276.
S. Ishimoto, Y. Etoh, T. Matsumoto, D. Lutz, A. Takagi, Improved Zr alloys for high burnup BWR fuel, Transactions of Top Fuel 2006, 2006 International Meeting on LWR Fuel Performance, Salamanca, Spain, Oct. 22–26 (2006).
W. J. O’Donnell and B. F. Langer, Fatigue Design Basis for Zircaloy Components, Nuclear Science and Engineering, 20, 1–12 (1964).
R.B. Adamson, C.E. Coleman, M. Griffiths, Irradiation creep and growth of zirconium alloys: A critical review, J. Nucl. Mater., 521 (2019) 167–244.
J. Gao, P. Song, Y.-J. Huang, K. Yabuuchi, A. Kimura, K. Sakamoto, S. Yamashita, Effects of neutron irradiation on 12Cr6Al-ODS steel with electron-beam weld line, J. Nucl. Mater, 524 (2019) 1–8.
Acknowledgments
Part of this study is the result of “Development of Technical Basis for Introducing Advanced Fuels Contributing to Safety Improvement of Current Light Water Reactors” program carried out by JAEA under the project on technical development for improving nuclear safety, supported by Ministry of Economy, Trade and Industry (METI) of Japan.
Author information
Authors and Affiliations
Corresponding author
Editor information
Editors and Affiliations
Rights and permissions
Copyright information
© 2024 The Author(s), under exclusive license to Springer Nature Singapore Pte Ltd.
About this paper
Cite this paper
Sakamoto, K. et al. (2024). Practical Development of Accident Tolerant Fecral-Ods Fuel Claddings for BWRs in Japan. In: Liu, J., Jiao, Y. (eds) Proceedings of the 2023 Water Reactor Fuel Performance Meeting. WRFPM 2023. Springer Proceedings in Physics, vol 299. Springer, Singapore. https://doi.org/10.1007/978-981-99-7157-2_3
Download citation
DOI: https://doi.org/10.1007/978-981-99-7157-2_3
Published:
Publisher Name: Springer, Singapore
Print ISBN: 978-981-99-7156-5
Online ISBN: 978-981-99-7157-2
eBook Packages: Physics and AstronomyPhysics and Astronomy (R0)