Temperature Dependence of Threshold Stress Intensity Factor, KIH in Zr-2.5Nb Alloy and Its Effect on Temperature Limit for Delayed Hydride Cracking

Article Preview

Abstract:

Threshold stress intensity factor or KIH required to initiate a delayed hydride crack in the axial direction of a Zr-2.5Nb tube was determined at temperatures of 160 oC to 280 oC. KIH remained constant at temperatures from 160 to 250 oC, increased with an increasing temperature in excess of 280 oC using a load decreasing method. To correlate KIH and dislocation twins, tensile tests were conducted on the Zr-2.5Nb tube and textural changes during tensile tests were investigated using an X-ray diffractometer. The extent of the twins increased from 150 to 300 oC and then decreased at temperatures in excess of 300 oC with no twins occurring at 350 oC. Temperature dependencies of KIH and a temperature limit for delayed hydride cracking were discussed with cracking of hydrides by the twins. This study provides supportive evidence to the feasibility of Kim’s DHC model.

You might also be interested in these eBooks

Info:

Periodical:

Key Engineering Materials (Volumes 326-328)

Pages:

919-922

Citation:

Online since:

December 2006

Export:

Price:

[1] L.A. Simpson and C.D. Cann: J. Nucl. Mater. Vol. 87 (1979) p.303.

Google Scholar

[2] Y.S. Kim, Y.G. Matvienko, Y.M. Cheong, S.S. Kim, S.C. Kwon: J. Nucl. Mater. Vol. 278 (2000) p.251.

Google Scholar

[3] S.Q. Shi and M.P. Puls: J. Nucl. Mater. Vol. 208 (1994) p.232.

Google Scholar

[4] M.R. Warren and G.J. Beevers: J. Nucl. Mater. Vol. 26 (1968) p.273.

Google Scholar

[5] D.G. Westlake: Trans. ASM. Vol. 56 (1963) p.1.

Google Scholar

[6] C.E. Coleman and D. Hardie: J. Less Common Met., Vol. 10 (1966) p.12.

Google Scholar

[7] S.S. Kim and Y.S. Kim: J. Kor. Inst. Met. & Mater. Vol. 38 (2000) p.985.

Google Scholar

[8] S. Sagat, C. E. Coleman, M. Griffiths, B. J. S. Wilkins, in: Ziconium in the Nuclear Industry, ASTM STP 1245, edited by A.M. Garde and E.R. Bradley, ASTM, Philadelphia (1994) p.35.

Google Scholar

[9] M.R. Levi and M.P. Puls, in : 18 th International Conference on Structural Mechanics in Reactor Technology (SMiRT 18), Beijing (2005), G10_3.

Google Scholar

[10] Y.S. Kim: Metals and Materials Int. Vol. 11 (2005) p.29.

Google Scholar

[11] Y.S. Kim, S.S. Kim, S.B. Ahn and Y.M. Cheong, in: Abstract booklet for 14th Symposium on Zirconium in the Nuclear Industry, ASTM, Stockholm, Sweden (2004).

Google Scholar

[12] A.P. Young and C.M. Schawartz, in: USAEC Report. No. BMI-1100. 1957. �.

Google Scholar