Influence of Specimen Configuration and TIG Welding on Fracture Toughness of RAFs (JLF-1)

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Abstract:

In order to apply a reduced activation ferritic (JLF-1) steel to the blanket/first-wall structure of a fusion reactor, its fracture toughness is very important for the strict estimation of material life. Fracture toughness testing of irradiated materials requires the use of miniaturised specimens and evaluation of TIG welding (tungsten inert gas arc welding) weldment properties is an important issue because necessary for production of nuclear fusion reactors. In this study, the fracture toughness tests were carried out according to the ASTM E1820-99. It was performed on various sizes (ligament and thickness) and various side-grooves of specimens and the TIG welding joint of JLF-1. The test results showed the standard specimen with side-groove of 40% represented valid fracture toughness. Fracture resistance curve (R-curve) increased with increasing specimen ligament and decreased with increasing specimen thickness. However, the R-curve of half size specimen was similar to that of the standard (1inch thickness) specimen. The fracture toughness test results of the TIG welded specimen showed a slight increase in the TIG welded specimen compared with JLF-1 base metal specimen.

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Key Engineering Materials (Volumes 297-300)

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788-793

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November 2005

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© 2005 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. Nucl. Mater. Vol. 193 (1998), pp.258-263.

Google Scholar

[2] A. Kohyama, A. Hishinuma, D.S. Gelles, R.L. Klueh, W. Dietz and K. Ehrlich: J. Nucl. Mater. Vol. 233-237 (1996), pp.138-147.

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

Google Scholar

[3] H.K. Yoon, S.W. Kim and S.P. Lee: International Journal of Modern Physics B Vol. 17 (2003), p.1547.

Google Scholar

[4] A. Kohyama, Y. Kohno, M. Kuroda, A. Kimura and F. Wan: J. Nucl. Mater. Vol. 58-263 (1998), p.1319.

Google Scholar

[5] G.E. Lucas, G.R. Odette, M. Sokolov, P. Spatig, T. Yamamoto and P. Jung: J. Nucl. Mater. Vol. 307-311 (2002), p.1600.

Google Scholar

[6] G.R. Odette, M. He, D. Gragg, D. Klingensmith and G.E. Lucas: J. Nucl. Mater. Vol. 307-311 (2002), p.1643.

Google Scholar

[7] C.S. Seok and S.Y. Kim: Nuclear Engineering and Design Vol. 214 (2002), pp.47-56.

Google Scholar

[8] C.S. Seok: KSME International J. Vol. 14 (2000), pp.11-18.

Google Scholar

[9] R. Moskovic, N.P. O'Dowd, M. Priest and P.E.J. Flewitt: Key Engineering Materials Vol. 251-252 (2003), pp.41-48.

Google Scholar

[10] H.K. Yoon, D.H. Kim, Y.H. Park, Y.S. Kong and A. Kohyama: Key Engineering Materials Vol. 261-263 (2004), pp.147-152.

Google Scholar