Document Type : Research Paper
Authors
Highlights
2. M. R. Louthan, R. P. Marshall, Control of hydride orientation in Zircaloy, J. Nuclear Material, 9 (1963) 170–184.
3. S. K. Yagnik, R-CKuo, Y. R. Rashid, A. J. Machiels, R. L. Yang, Effect of hydrides on the mechanical properties of Zircaloy-4, Proc. 2004 Int. Meeting on LWR Fuel Performance, Orland, Florida, Sept. 19–22, 2004, 1089, (2004) 191-199.
4. J. Bai, C. Prioul, D. Francois, Hydride embrittlement in Zircaloy-plate: part 1. Influence of microstructure on the hydride embrittlement in Zircaloy-4 at 20C and 350C, Metall. Trans. A, 25A (1994) 1185-1197.
5. S. Shimada, E. Etoh, H. Hayashi, Y. Tukuta, A metallographic and fractographic study of outside-in cracking caused by power ramp tests, J. Nuclear Material, 327 (2004) 97–113.
6. F. Nagase, T. Fuketa, Influence of hydride re-orientation on BWR cladding rupture under accidental conditions, J. Nuclear Science Tech., 41 [12] (2004) 1211–1217.
7. D. Hardie, M. W. Shanahan, Stress reorientation of hydrides in zirconium-2.5% niobium, J. Nuclear Material, 55 (1975) 1–13.
8. G. W. Parry, Stress reorientation of hydrides in cold-worked Zirconium-2.5% Niobium pressure tubes, AECL-2624, 1 (1996).
9. R. P. Marshall, Influence of fabrication history on stress-oriented hydrides in Zircaloy tubing, J. Nuclear Material, 24 (1967) 34–48.
10.J. J. Kearns, C. R. Woods, Effect of texture, grain size, and cold work on the precipitation of oriented hydrides in Zircaloy tubing and plate, J. Nuclear Material, 20 (1966) 241–261.
11.M. Leger, A. Donner, The effect of stress on orientation of hydrides in zirconium alloy pressure tube materials, Can. Metall. Q., 24[3] (1985) 235–243.
12.J. B. Bai, C. Prioul, D. Francois, Effect of microstructure factors and cold work on the hydride precipitation in Zircaloy-4 sheet, J. Adv. Science, 3[4] (1991) 188.
13.Y. Mishima, T. Okubo, Effect of thermal cycling on the stress orientation and circumferential ductility in Zircaloy-2, Can. Metall. Q., 11[1] (1972) 157–164.
14.R. P. Marshall, Control of hydride orientation in Zircaloy by fabrication practice, J. Nuclear Material, 24 (1967) 49–59.
15.P. Rudling and G. Wikmark, A unified model of Zircaloy BWR corrosion and hydriding mechanisms, J. Nuclear Material, 265 (1999) 44-59.
Keywords
2. M. R. Louthan, R. P. Marshall, Control of hydride orientation in Zircaloy, J. Nuclear Material, 9 (1963) 170–184.
3. S. K. Yagnik, R-CKuo, Y. R. Rashid, A. J. Machiels, R. L. Yang, Effect of hydrides on the mechanical properties of Zircaloy-4, Proc. 2004 Int. Meeting on LWR Fuel Performance, Orland, Florida, Sept. 19–22, 2004, 1089, (2004) 191-199.
4. J. Bai, C. Prioul, D. Francois, Hydride embrittlement in Zircaloy-plate: part 1. Influence of microstructure on the hydride embrittlement in Zircaloy-4 at 20C and 350C, Metall. Trans. A, 25A (1994) 1185-1197.
5. S. Shimada, E. Etoh, H. Hayashi, Y. Tukuta, A metallographic and fractographic study of outside-in cracking caused by power ramp tests, J. Nuclear Material, 327 (2004) 97–113.
6. F. Nagase, T. Fuketa, Influence of hydride re-orientation on BWR cladding rupture under accidental conditions, J. Nuclear Science Tech., 41 [12] (2004) 1211–1217.
7. D. Hardie, M. W. Shanahan, Stress reorientation of hydrides in zirconium-2.5% niobium, J. Nuclear Material, 55 (1975) 1–13.
8. G. W. Parry, Stress reorientation of hydrides in cold-worked Zirconium-2.5% Niobium pressure tubes, AECL-2624, 1 (1996).
9. R. P. Marshall, Influence of fabrication history on stress-oriented hydrides in Zircaloy tubing, J. Nuclear Material, 24 (1967) 34–48.
10.J. J. Kearns, C. R. Woods, Effect of texture, grain size, and cold work on the precipitation of oriented hydrides in Zircaloy tubing and plate, J. Nuclear Material, 20 (1966) 241–261.
11.M. Leger, A. Donner, The effect of stress on orientation of hydrides in zirconium alloy pressure tube materials, Can. Metall. Q., 24[3] (1985) 235–243.
12.J. B. Bai, C. Prioul, D. Francois, Effect of microstructure factors and cold work on the hydride precipitation in Zircaloy-4 sheet, J. Adv. Science, 3[4] (1991) 188.
13.Y. Mishima, T. Okubo, Effect of thermal cycling on the stress orientation and circumferential ductility in Zircaloy-2, Can. Metall. Q., 11[1] (1972) 157–164.
14.R. P. Marshall, Control of hydride orientation in Zircaloy by fabrication practice, J. Nuclear Material, 24 (1967) 49–59.
15.P. Rudling and G. Wikmark, A unified model of Zircaloy BWR corrosion and hydriding mechanisms, J. Nuclear Material, 265 (1999) 44-59.