Fracture toughness of irradiated Zr–2.5Nb pressure tube from Indian PHWR
Source abstract
Abstract
Abstract Fracture toughness of irradiated Zr–2.5Nb alloy pressure tube, fabricated by the cold pilgering and stress relieving route, was evaluated using disk compact tension type specimens. These specimens were punched out from the irradiated pressure tube (S-07), which was in service for about 8 effective full power years of reactor operation in the Kakrapar Atomic Power Station-2 (KAPS-2). The tests were carried out remotely inside a lead shielded enclosure. Crack growth during the test was measured using the direct current potential drop technique. The irradiated pressure tube showed low fracture toughness at 25 °C. The fracture toughness increased with increase in temperature up to 250 °C but was practically unaffected with further increase in temperature up to 300 °C. This paper discusses the fracture behavior of irradiated Indian pressure tube material and compares it with other data available.
Source: openaire · Quality: candidate unverified · Source record ↗
Research context
OpenAlex topics: Nuclear Materials and Properties · Fusion materials and technologies · Nuclear reactor physics and engineering
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References (17)
Show source-provided references
1. Singh · J. Nucl. Mat. · 2013 · 432 · 8710.1016/j.jnucmat.2012.07.046 ↗
2. Singh · Mater. Sci. Eng. A · 2009 · 523 · 11210.1016/j.msea.2009.05.066 ↗
3. C. Ganguly, Advances in Zirconium technology for nuclear reactor application, in: Proc. of the Symposium Zirconium 2002, ZIRC 2002, Mumbai, India, pp. 1–27.
4. Sah · J. Nucl. Mat. · 2008 · 383 · 12810.1016/j.jnucmat.2008.08.054 ↗
5. B.N. Rath, H.N. Singh, J.L. Singh, P.M. Ouseph, D.N. Sah, BARC Internal Report BARC/2006/I/014.
6. Standard test method for measurement of fracture toughness, ASTM E1820-11.
7. P.H. Davies, R.R. Hosbons, M. Griffiths, C.K. Chow, ASTM STP 1245, 1993, pp. 135–167.10.1520/STP15188S ↗
8. Langford · Int. J. Press. Vessel Pip. · 1978 · 6 · 27510.1016/0308-0161(78)90013-3 ↗
9. Cowen · J. Nucl. Mat. · 1969 · 30 · 27110.1016/0022-3115(69)90242-6 ↗
10. B.J.S. Wilkins, J.N. Barrie, R.J. Zink, Report AECL-6195, 1978.
11. C.K. Chow, C.E. Coleman, R.R. Hosbons, P.H. Davies, M. Griffiths, R. Choubey, ASTM STP 1132, 1991, pp. 246–275.10.1520/STP25511S ↗
12. C.K. Chow, L.A. Simpson, ASTM STP 945, 1988, pp. 419–439.
13. P.H. Davies, R.S.W. Shewfelt, ASTM STP 1295, 1996, pp. 492–517.10.1520/STP16187S ↗
14. S. Chatterje, P.K. Shah, J.S. Dubey, BARC External Report BARC/2008/E/008.
15. L.A. Simpson, C.F. Clarke, ASTM STP 668, 1979, pp. 643–662.10.2118/7500-PA ↗
16. P.H. Davies, D.D. Himbeault, R.S.W. Shewfelt, R.R. Hosbons, ASTM STP 1405, 2001, pp. 846–868.10.1520/STP10577S ↗
17. Seung-Jin Oh, In-Sup Kim, Young-Suk Kim, Sang-Bok Ahn, in: 18th International Conference on Structural Mechanics in Reactor Technology (SMiRT 18), SMiRT18-C04-1, 2005.