Abstract
Irradiation-resistant materials R&D are one of the key issues to realize fusion power reactor because 14 MeV fusion neutrons will give severe degradation to the structural materials through significant displacement damage with a large amount of transmutation helium up to several thousand appm. When these helium atoms diffuse onto grain boundaries, it can lead to degradation of toughness through intergranular fracture. The present paper describes superior resistance of oxide dispersion strengthened (ODS) ferritic steels to the intergranular fracture due to helium. Dual-beam ion-irradiation technique was applied to reveal the helium effect on the microstructural evolution and mechanical property change of the ODS ferritic steels as well as of the non-ODS ferritic steels.
This is a preview of subscription content, log in via an institution to check access.
Access this chapter
Tax calculation will be finalised at checkout
Purchases are for personal use only
References
Kimura A, Kasada R, Kohyama A, Tanigawa H, Hirose T, Shiba K, Jitsukawa S, Ohtsuka S, Ukai S, Sokolov MA, Klueh RL, Yamamoto T, Odette GR (2007) Recent progress in US–Japan collaborative research on ferritic steels R&D. J Nucl Mater 367–370:60–67
Norajitra P, Bühler L, Fischer U, Malang S, Reimann G, Schnauder H (2002) The EU advanced dual coolant blanket concept. Fusion Eng Des 61–62:449–453
Reiser J, Norajitra P, Ruprecht R (2008) Numerical investigation of a brazed joint between W-1%La2O3 and ODS EUROFER components. Fusion Eng Des 83:1126–1130
Hasegawa A, Ejiri M, Nogami S, Ishiga M, Kasada R, Kimura A, Abe K, Jitsukawa S (2009) Effects of helium on ductile–brittle transition behavior of reduced-activation ferritic steels after high-concentration helium implantation at high temperature. J Nucl Mater 386–388:241–244
Yutani K, Kishimoto H, Kasada R, Kimura A (2007) Evaluation of helium effects on swelling behavior of oxide dispersion strengthened ferritic steels under ion irradiation. J Nucl Mater 367–370:423–427
Kasada R, Takahashi H, Kishimoto H, Yutani K, Kimura A (2010) Superior radiation resistance of ODS ferritic steels. Mater Sci Forum 654–656:2791–2794
Ukai S, Fujiwara M (2002) Perspective of ODS alloys application in nuclear environments. J Nucl Mater 307–311:749–757
Klueh RL, Gelles DS, Jitsukawa S, Kimura A, Odette GR, Van der Schaaf B, Victoria M (2002) Ferritic/martensitic steels – overview of recent results. J Nucl Mater 307–311:455–465
Oliver WC, Pharr GM (2004) Measurement of hardness and elastic modulus by instrumented indentation: advances in understanding and refinements to methodology. J Mater Res 19:3–20
Ohnuma M, Suzuki J, Ohtsuka S, Kim S-W, Kaito T, Inoue M, Kitazawa H (2009) A new method for the quantitative analysis of the scale and composition of nanosized oxide in 9Cr-ODS steel. Acta Mater 57:5571–5581
Yutani K, Kasada R, Kishimoto H, Kimura A (2007) Irradiation hardening and microstructure evolution of ion-irradiated ODS ferritic steels. J ASTM Int 4, JAI100701
Author information
Authors and Affiliations
Corresponding author
Editor information
Editors and Affiliations
Rights and permissions
Copyright information
© 2011 Springer
About this paper
Cite this paper
Kasada, R., Takahashi, H., Yutani, K., Kishimoto, H., Kimura, A. (2011). Helium Ion Irradiation Effects in ODS and Non-ODS Ferritic Steels. In: Yao, T. (eds) Zero-Carbon Energy Kyoto 2010. Green Energy and Technology. Springer, Tokyo. https://doi.org/10.1007/978-4-431-53910-0_40
Download citation
DOI: https://doi.org/10.1007/978-4-431-53910-0_40
Publisher Name: Springer, Tokyo
Print ISBN: 978-4-431-53909-4
Online ISBN: 978-4-431-53910-0
eBook Packages: EngineeringEngineering (R0)