journal article·2015-12

Effect of specimen thickness on DHC velocity for Zr-2.5Nb alloy pressure tube material

S. Sunil, A.K. Bind, H.K. Khandelwal, R.N. Singh, J.K. Chakravartty

Publisher page

Abstract

Abstract Zr-2.5Nb alloy pressure tubes used in pressurized heavy water reactors (PHWR) are susceptible to failure by Delayed Hydride Cracking (DHC), which is a form of localized hydride-embrittlement phenomenon manifested in the presence of a hydrostatic stress gradient and hydrogen concentration above a threshold limit as a sub-critical crack growth process in hydride forming metals. The DHC parameters used for safety assessment are DHC velocity (VDHC) and a threshold stress intensity factor (KIH). In this work DHC velocity was determined for Zr-2.5Nb pressure tube material at 250 and 280 °C using specimens of thickness between 1 mm and 4.5 mm. The DHC velocity was found to increase with increase in specimen thickness at 250 °C and 280 °C. Significant amount of tunneling of the crack was observed for 1-mm and 2-mm thick specimens at 250 °C and 280 °C, with the degree of tunneling increasing with decrease in thickness and increase in test temperature.
Source: openaire · Quality: candidate unverified · Source record ↗

Research context

OpenAlex topics: Nuclear Materials and Properties · Fusion materials and technologies · Hydrogen embrittlement and corrosion behaviors in metals

SciVX discovery tags are terminology-based. OpenAlex topics are source-provided classifications.

References (25)

Show source-provided references
1. Northwood · J. Nucl. Mater. · 1978 · 78 · 11210.1016/0022-3115(78)90509-3 ↗
2. Singh · Mater. Sci. Eng. A · 2009 · 523 · 11210.1016/j.msea.2009.05.066 ↗
3. R. Choubey, FC-IAEA-02 T1.20.13-CAN-273.63–02 (1998).10.1142/S0217751X98000123 ↗
4. Dutton · Metall. Trans. A · 1977 · 8 · 155310.1007/BF02644858 ↗
5. Puls · J. Nucl. Mater. · 2009 · 393 · 35010.1016/j.jnucmat.2009.06.022 ↗
6. Hydride induced embrittlement of zirconium alloy pressure tubes
7. Dutton · 1976 · 512
8. Puls · Metall. Trans. A · 1990 · 21 · 290510.1007/BF02647211 ↗
9. Yan · Int. J. Press. Vessels Pip. · 2000 · 77 · 16710.1016/S0308-0161(99)00081-2 ↗
10. Effect of stress state and texture on delayed hydride cracking; kinetics in reactor pressure tubes
11. Coleman · Nucl. Eng. Technol. · 2009 · 41 · 110.5516/NET.2009.41.2.171 ↗
12. IAEA, TECDOC1037, August (1998) 19.
13. Srivastava · Metall. Mater. Trans. A · 1995 · 26 · 270710.1007/BF02669427 ↗
14. Northwood · Int. Met. Rev. · 1983 · 28 · 9210.1179/imr.1983.28.1.92 ↗
15. Singh · Mater. Sci. Eng. A · 2004 · 374 · 34210.1016/j.msea.2004.03.008 ↗
16. Hutchinson · J. Mech. Phys. Solids · 1968 · 16 · 1310.1016/0022-5096(68)90014-8 ↗
17. Rice · J. Mech. Phys. Solids · 1968 · 16 · 110.1016/0022-5096(68)90013-6 ↗
18. Shek · J. Nucl. Mater. · 1996 · 231 · 22110.1016/0022-3115(96)00370-4 ↗
19. Sagat · 1994 · 1245 · 35
20. Shi · J. Nucl. Mater. · 1994 · 208 · 23210.1016/0022-3115(94)90332-8 ↗
21. Zirconium in the Nuclear Industry
22. Singh · 2007 · vol. 3 · 81
23. IAEA, TECDOC, 1649.
24. Carpenter · J. Nucl. Mater. · 1973 · 48 · 26410.1016/0022-3115(73)90022-6 ↗
25. Singh · J. Alloys Compd. · 2007 · 436 · 15010.1016/j.jallcom.2006.07.049 ↗