journal article·2017-12

Effect of deuterium content on fracture toughness of Zr-2.5Nb pressure tube material in the temperature range of ambient to 300 °C

A.K. Bind, R.N. Singh, Saurav Sunil, J. Chattopadhyay

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Abstract

Abstract Axial fracture toughness of cold worked and stress relieved Zr-2.5Nb pressure tube material containing deuterium between 5 and 200wppm was determined as per ASTM E−1820-15 between 25 and 300 °C using 17 mm wide Curved Compact Tension samples. For deuterium charged materials, the variation of the fracture toughness with test temperature showed typical S curve behavior. At 25 °C, the fracture toughness dropped drastically between 5 and 30wppm of deuterium concentration and afterwards it was constant between 30 and 200wppm. Samples having similar axial split density had similar fracture toughness. The lower-shelf and upper-shelf temperature was attributed to a critical axial split density and disappearance of axial split on fracture surface, respectively.
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OpenAlex topics: Nuclear Materials and Properties · Fusion materials and technologies · Nuclear reactor physics and engineering

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References (38)

Show source-provided references
1. CANDU-PHW pressure tubes: their manufacture, inspection, and properties10.13182/NT82-A26307 ↗
2. Ross-Ross · 1968
3. An improvement in creep resistance of Zr-2.5%Nb tubes10.1016/0022-3115(75)90209-3 ↗
4. Development of zirconium alloys for pressure tubes in Candu reactors10.1179/cmq.1985.24.3.273 ↗
5. Assessment of hydrogen embrittlement of Zircaloy-2 pressure tubes using unloading compliance and load normalization techniques for determining J-R curves10.1016/S0022-3115(98)00487-5 ↗
6. Delayed hydride cracking in Zr–2.5Nb pressure tube material10.1016/S0022-3115(02)00880-2 ↗
7. Technology of reactor RBMK pressure tubes from Zr–2.5% Nb alloy, Problems of atomic science and technology
8. Oxidation and deuterium uptake of Zr-2.5Nb pressure tubes in CANDU-PHW reactors
9. Hydrides and delayed hydrogen cracking in zirconium and its alloys
10. Influence of hydrogen content on impact toughness of Zr-2.5Nb pressure tube Alloy10.1016/j.nucengdes.2011.04.024 ↗
11. The terminal solid solubility of hydrogen and deuterium in Zr2.5Nb alloys10.1016/S0022-3115(95)00217-0 ↗
12. Analysis of the pressure tube failure at Pickering NGS A unit 2 Nuclear systems department10.1179/cmq.1985.24.3.181 ↗
13. Assessment of aging of Zr-2.5Nb pressure tubes in CANDUTM reactors10.1016/S0029-5493(96)01310-6 ↗
14. G.D. Maon, P.J. Richinson, Leak before break in CANDU pressure tubes: Recent advances, Pressure vessel and piping conference 1993, Denver, CO, USA, 25-29 Jul. 1993 266 (1993) 205–215.
15. Influence of hydrogen content on fracture toughness of CWSR Zr–2.5Nb pressure tube alloy10.1016/j.jnucmat.2012.07.046 ↗
16. Fracture toughness evaluation of Zr-2.5Nb pressure tubes manufactured employing double forging for PHWR700
17. Influence of loading rate and hydrogen content on fracture toughness of Zr-2.5Nb pressure tube material10.1016/j.jnucmat.2015.05.050 ↗
18. Effect of direction of approach of test temperature on fracture toughness of Zr-2.5Nb pressure tube material10.1016/j.msea.2014.10.052 ↗
19. Correlation between irradiated and unirradiated fracture toughness of Zr-2.5Nb pressure tubes
20. Crack growth resistance of irradiated Zr-2.SNb pressure tube material at low hydrogen levels
21. Effect of irradiation on the fracture properties of Zr-2.5Nb pressure tubes at the end of design life
22. Temperature dependence of misfit strains of δ-hydrides of zirconium10.1016/j.jallcom.2006.07.049 ↗
23. Effect of hydrogen isotope content on tensile flow behavior of Zr-2.5Nb pressure tube material between 25 and 300 °C10.1016/j.jnucmat.2016.04.019 ↗
24. Sawatzky · 1964
25. 1820
26. Effects of crack tip stress states and hydride-matrix interaction stresses on delayed hydride cracking10.1007/BF02647211 ↗
27. Effects of hydride morphology on Zr–2.5Nb fracture toughness
28. Srivastava · 2011
29. Evolution of microstructure during fabrication of Zr-2.5 Wt. pct. Nb alloy pressure tube10.1007/BF02669427 ↗
30. J-R curve determination for disk-shaped compact specimens based on the normalization method and the direct current potential drop technique
31. A DC potential drop procedure for crack initiation and R-curve measurements during ductile fracture tests
32. An investigation of the blunting line10.1016/0013-7944(83)90074-7 ↗
33. Influence of stress field of expanding and contracting plate shaped precipitate on hydride embrittlement of Zr-alloys10.1016/j.msea.2013.04.117 ↗
34. Crack initiation criterion at notches in Zr-2.5Nb alloys10.1016/0921-5093(94)90981-4 ↗
35. Price · 1988
36. Comparison of J-parameters of cold worked and stress relieved Zr–2.5Nb pressure tube alloy determined using load normalization and direct current potential drop technique10.1016/j.engfracmech.2013.04.003 ↗
37. Racture toughness of irradiated Zr–2.5Nb pressure tube from Indian PHWR10.1016/j.jnucmat.2014.12.066 ↗
38. Delayed hydride crack growth study on irradiated Zr–2.5Nb pressure tube10.1016/j.jnucmat.2015.01.046 ↗