Evaluation Strength and Fracture Toughness of Reduced Activation Ferritic Steel (JLF-1) for Fusion Reactor

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Abstract:

Reduced activation ferritic (JLF-1) steel is one of the leading candidates for blanket/first-wall structures in D-T fusion reactors. In fusion applications, structural materials will suffer the effects of repeated temperature changes. Therefore, a database of tensile strength and fracture toughness are very important as the temperature is 400 ° C and it's TIG welded joint. In this paper, fracture toughness JIC and KIC) and tensile tests were carried out at room temperature (RT) and at elevated temperature (400 ° C). The tensile properties of the TIG welding joint of JLF-1 steel was also investigated. It was shown that the tensile strength and fracture toughness values of the JLF-1 steel are slightly decreased with as increase in temperature. The fracture toughness values of JLF-1 steel at room temperature and at 400°C show excellent JIC values of about 530 kJ/m2 and 340 kJ/m2, respectively.

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Key Engineering Materials (Volumes 261-263)

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147-152

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April 2004

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© 2004 Trans Tech Publications Ltd. All Rights Reserved

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[1] A. Hishinuma, A. Kohyama, R.L. Kludo, D.S. Gelles, W. Dietz and K. Ehrlich, J. of Nuclear Materials, 258-263 (1998) p.193.

DOI: 10.1016/s0022-3115(98)00395-x

Google Scholar

[2] F. Abe, A. Hishinuma, A. Kohyama and M. Suzuki (Eds. ), Proc. IEA Workshop on Ferritic/ Martensitic Steels, JAERI (1993).

Google Scholar

[3] R.L. Klueh, K. Ehrlich and F. Abe, J. of Nuclear Materials, 166 (1992) pp.191-194.

Google Scholar

[4] Y. Kohno, Annual Progress Report of Japan/US Collaborative Research Utilizing the FFTF/ MOTA, National Institute for Fusion Science (1997) p.73.

Google Scholar

[5] A. Kohyama, A. Hishinuma, D.S. Gelles, R.L. Klueh, W. Dietz and K. Ehrlich, J. of Nuclear Materials, 138, (1996) p.233.

DOI: 10.1016/s0022-3115(96)00327-3

Google Scholar

[6] A. Nishimura, N. Inoue and T. Muroga, J. of Nuclear Materials, 258-263 (1998) p.1242.

Google Scholar

[7] Y. Kohno, A. Kohyama, T. Hirose, M.L. Hamilton and M. Narui, J. of Nuclear Materials, 271- 272, (1999) p.145.

DOI: 10.1016/s0022-3115(98)00735-1

Google Scholar

[8] K. Shiba, A. Hishinuma, A. Kohyama and K. Masamura, Japan Atomic Energy Research Institute, JAERI-Tech, 97-038 (1997) p.29.

Google Scholar

[9] K. Shiba, R.L. Klueh, Y. Miwa, J.P. Robertson and A. Hishinuma, J. of Nuclear Materials, 283- 287 (2000) p.358.

DOI: 10.1016/s0022-3115(00)00362-7

Google Scholar

[10] P. Spatig, G. r. Odette, E. Donahue and G.E. Lucas, J. of Nuclear Materials Vol. 283-287 (2000) pp.721-726.

Google Scholar