Abstract
The nuclear grade 304NG stainless steel (SS) has been developed in the past several decades as the new generation of internal material in light water reactors. The irradiation effects of domestic 304NG SS were simulated by the triple ion beam irradiation on the heavy ion, hydrogen and helium triple ion beam irradiation platform at China institute of Atomic Energy. The irradiation experiments were carried out with various doses (6, 15, 30 and 150 dpa at 300 ℃) and temperatures (300, 350, 400, 450 ℃ with 6 dpa). The depth-dependent hardness and elastic modulus of the specimens before and after irradiation were measured by nanoindentation with the continuous stiffness measurement technique. For the specimens irradiated at 300 ℃, the hardness generally increases with the increasing dose. The depth-dependent hardness in the micro-indentation region (indentation depth h > 100 nm) of those specimens with dose less than 30 dpa can be well explained by Nix & Gao formulae of the indentation size effect. For the specimens irradiated at different temperatures, the hardening effect can be observed for all specimens for indentation depth beyond 1 μm and the hardness decreases with increasing irradiation temperature. However, as the irradiation temperature elevates or the dose increases up to 150 dpa, the hardness for the indentation depth h < 500 nm deviates significantly from the projection of the Nix & Gao model. The surface morphology observed by SEM and the S parameters extracted from the slow positron annihilation Doppler broadening indicate that the drastic reduction of hardness those specimens with indentation depth h < 500 nm can be attributed to the change of surface morphology.
Access this chapter
Tax calculation will be finalised at checkout
Purchases are for personal use only
References
H. Wolfgang, Materials for nuclear plants: from safe design to residual life assessments (Springer, London, 2013)
T. Allen, J. Busby, M. Meyer, D. Petti, Materials challenges for nuclear systems. Mater. Today 13, 14 (2010)
Y. Wen, X.-P. Lai, Y.-G. Duan, E. Jiang, G.-F. Li, B. Xu, B. Gong, Research on application performance of nitrogen-containing stainless steel 304NG made in China. Nucl. Power Eng. 28(z1), 40–43 (2007). (in Chinese)
Y.J. Wei, D.H. Xia, S.Z. Song, Detection of SCC of 304NG stainless steel in an acidic NaCl solution using electrochemical noise based on chaos and wavelet analysis. Russ. J. Electrochem. 52, 560–575 (2016)
J.E. Alexander, et al., Alternative alloys for BWR piping applications, Final Report, NP-2671-LD, General Electric Company, October (1982)
R.W. Weeks, Stress-corrosion cracking in BWR and PWR piping, Proceedings of the International Symposium on Environmental Degradation of Materials in Nuclear Power Systems—Water Reactors: Myrtle Beach, South Carolina, August 22–25, (1983)
Q. Luo, Y. Chen, S. Liu, The studies on the corrosion behaviors of 316NG and 304NG nitrogen-containing stainless steels made in China. Procedia Eng. 27, 1560–1567 (2012)
ASTM E521-16, Standard practice for investigating the effects of neutron radiation damage using charged-particle irradiation, ASTM International, West Conshohocken, PA, (2016). www.astm.org
G.S. Was, Fundamentals of radiation materials science: metals and alloys (Springer, Berlin, 2007)
E.H. Lee, J.D. Hunn, G.R. Rao, R.L. Klueh, L.K. Mansur, Triple ion beam studies of radiation damage in 9Cr-2WVTa ferritic martensitic steel for a high power spallation neutron source. J. Nucl. Mater. 271, 385–390 (1999)
T. Tanaka, K. Oka, S. Ohnuki, S. Yamashita, T. Suda, S. Watanabe, E. Wakai, Synergistic effect of helium and hydrogen for defect evolution under multi-ion irradiation of Fe–Cr ferritic alloys. J. Nucl. Mater. 329–333, 294–298 (2004)
D.-Q. Yuan, Y.-N. Zhen, Y. Zuo, P. Fan, D.-M. Zhou, Q.-L. Zhang, X.-Q. Ma, B.-Q. Cui, L.-H. Chen, W.-S. Jiang, Y.-C. Wu, Q.-Y. Huan, L. Pen, X.-Z. Cao, B.-Y. Wang, L. Wei, S.-Y. Zhu, Synergistic effect of triple ion beams on radiation damage in CLAM steel. Chin. Phys. Lett. 31, 2012–2014 (2014)
L.R. Greenwood, F.A. Garner, Hydrogen generation arising from the 59Ni(n, p) reaction and its impact on fission–fusion correlations. J. Nucl. Mater. 233, 1530 (1996)
J. Biersack, L. Haggmark, A Monte Carlo computer program for the transport of energetic ions in amorphous targets. Nucl. Instr. Meth. 174, 257 (1980)
J.F. Ziegler, M.D. Ziegler, J.P. Biersack, SRIM—The stopping and range of ions in matter (2010). Nucl. Instr. Meth. Phys. Res. B 268, 1818 (2010)
W.C. Oliver, G.M. Pharr, An improved technique for determining hardness and elastic modulus using load and displacement sensing indentation experiments. J. Mater. Res. 7, 1564 (1992)
B.Y. Wang, X.Z. Cao, R.S. Yu et al., The slow positron beam based on beijing electron-positron collider. Mater. Sci. Forum 445–446, 513–515 (2004)
W.D. Nix, H.J. Gao, Indentation size effects in crystalline materials: a law for strain gradient plasticity. J. Mech. Phys. Solids 46, 411–425 (1998)
G.M. Pharr, E.G. Herbert, Y. Gao, The indentation size effect: a critical examination of experimental observations and mechanistic interpretations. Annu. Rev. Mater. Res. 40, 271–292 (2010)
H. Zhang, C. Zhang, Y. Yang, Y. Meng, J. Jang, A. Kimura, Irradiation hardening of ODS ferritic steels under helium implantation and heavy-ion irradiation. J. Nucl. Mater. 455, 349–353 (2014)
X. Bai, S. Wu, P.K. Liaw, L. Shao, J. Gigax, Effect of heavy ion irradiation dosage on the hardness of SA508-IV reactor pressure vessel steel. Metals (Basel) 7, 1–11 (2017)
Y. Liu, A.H.W. Ngan, Depth dependence of hardness in copper single crystals measured by nanoindentation. Scr. Mater 44, 237–241 (2001)
Z. Wang, Influences of sample preparation on the indentation size effect and nanoindentation pop-in on nickel. Ph.D. dissertation, University of Tennessee, 2012
M.J. Puska, R.M. Nieminen, Theory of positrons in solids and on solid surfaces. Rev. Mod. Phys. 66(3), 841–897 (1994)
A. Vehanen, K. Saarinen, P. Hautojärvi, H. Huomo, Profiling multilayer structures with monoenergetic positrons. Phys. Rev. B 35, 4606 (1987)
Acknowledgements
The authors acknowledge the support from the National Science Foundation of China under Grant No. 11005158 and 9112600, and the National major project of science and technology under Grant No. 2012ZX06004-005-005.
Author information
Authors and Affiliations
Corresponding author
Editor information
Editors and Affiliations
Rights and permissions
Copyright information
© 2018 Springer Nature Singapore Pte Ltd.
About this paper
Cite this paper
Ma, H. et al. (2018). Irradiation Hardening and Indentation Size Effect of the 304NG Stainless Steels After Triple Beam Irradiation. In: Han, Y. (eds) Advances in Energy and Environmental Materials. CMC 2017. Springer Proceedings in Energy. Springer, Singapore. https://doi.org/10.1007/978-981-13-0158-2_21
Download citation
DOI: https://doi.org/10.1007/978-981-13-0158-2_21
Published:
Publisher Name: Springer, Singapore
Print ISBN: 978-981-13-0157-5
Online ISBN: 978-981-13-0158-2
eBook Packages: EnergyEnergy (R0)