Miniature impact test technique to evaluate the orientation dependence of impact toughness of hydrided Zr–2.5%Nb alloy
Source abstract
Abstract
Miniature Impact test technique was used to investigate the plausible role of hydride platelet orientation relative to the crack plane on the fracture mechanism of the Zr–2.5%Nb alloy over a wide range of temperatures. Miniature impact samples were fabricated from spools of un-hydrided (UH), circumferential hydrided (CH) and radial hydrided (RH) materials with different combinations of crack plane normal and crack growth direction. The impact tests were carried out between − 50 to 300 °C. Both microstructural (microstructure, texture) and fractographic examinations were carried out. The extent of hydride embrittlement and temperature dependence of the impact toughness were explained in terms of the hydride platelet orientation with respect to the crack plane and solubility of hydrogen in the material at different test temperatures. Graphical abstract Variation of impact energy with test temperature for un-hydrided, circumferential and radial hydrided samples for a CA (Radial hydride lying parallel to the crack plane) and b AC (Both circumferential and radial hydride oriented normal to crack plane)
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Research context
OpenAlex topics: Nuclear Materials and Properties · Fusion materials and technologies · Powder Metallurgy Techniques and Materials
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References (32)
Show source-provided references
1. ASTM E23–16b (2016) Standard test methods for notched bar impact testing of metallic materials, Title, ASTM Int. West Conshohocken, PA. https://doi.org/10.1520/E0023-12C10.1520/E0023-12C ↗
2. Bind AK, Sunil S, Singh RN (2016) Effect of hydrogen isotope content on tensile flow behavior of Zr–2.5Nb pressure tube material between 25 and 300 °C. J Nucl Mater 476:5–12. https://doi.org/10.1016/j.jnucmat.2016.04.01910.1016/j.jnucmat.2016.04.019 ↗
3. Coleman CE, Cheadle BA, Theaker JR, Cann CD (1996), Development of pressure tubes with service life greater than 30 years, American Society for Testing and Materials, United States. http://inis.iaea.org/search/search.aspx?orig_q=RN:28058384.
4. Coleman CE, Cheadle BA, Causey AR, Doubt GL, Fong RWL, Venkatapathi S (1996) Improving the service life and performance of CANDU fuel channels. Atomic Energy of Canada Ltd.
5. Davies PH, Stearns CP (1986) Fracture toughness testing of Zircaloy-2 pressure tube material with radial hydrides using direct-current potential drop, in: Fract. Mech. Seventeenth Vol., ASTM International10.1520/STP17408S ↗
6. Dietz W (1994) Structural materials. In: Cahn RW, Haasen P, Kramer EJ (eds) Materials science and technology: a comprehensive treatment, nuclear materials. Wiley, Weinheim, pp 56–172
7. Fleck RG, Price EG, Cheadle BA (1984), Pressure Tube Development for CANDU Reactors. In: Franklin DG, Adamson RB (Eds.), Zircon. Nucl. Ind., ASTM International, West Conshohocken, PA, pp 88–105. https://doi.org/10.1520/STP34464S.10.1520/STP34464S ↗
8. Haggag FM (1993) Effect of irradiation temperature on embrittlement of nuclear pressure vessel steels, effects of radiation on materials: 16th International Symposium, ASTM STP 1175, Kumar Arvind S, Gelles David S,Nanstad Randy K and Little Edward A, Eds., American Society for Testing and Materials, Philadelphia, pp 172–185
9. Hoffmann M, Birringer R (1995) Mater Sci Eng A 202:18–25. https://doi.org/10.1016/0921-5093(95)09817-810.1016/0921-5093(95)09817-8 ↗
10. Huang FM, Hamilton ML, Wire GL (1982) Bend testing for miniature disks. Nucl Tech 57:234–242. https://doi.org/10.13182/NT82-A2628610.13182/NT82-A26286 ↗
11. Khatamian D, Ling VC (1997) Hydrogen solubility limits in α-and β-zirconium. J Alloys Compd 253:162–166. https://doi.org/10.1016/S0925-8388(96)02947-710.1016/S0925-8388(96)02947-7 ↗
12. Kotak SP, Dubey JS, Singh RN, Kumar A, Rath BN (2017) Effect of specimen geometry, orientation and temperature on the impact toughness of Zr-25Nb pressure tube. In: Charit I, Zhu Y, Maloy S, Liaw P (eds) Mechanical and creep behavior of advanced materials. The minerals, metals & materials series. Springer, Cham
13. Kundan K, Arun P, Madhusoodanan K, Singh RN, Arnomitra C, Dutta BK, Sinha RK (2016) Optimisation of thickness of miniature tensile specimens for evaluation of mechanical properties. Mat Sci Eng A 675:32–43. https://doi.org/10.1016/j.msea.2016.08.03210.1016/j.msea.2016.08.032 ↗
14. Kwon J, Huh H, Kim J (2017) Evaluation of the ductile-to-brittle transition temperature of a silicon steel under various strain rate conditions with a servo-hydraulic high speed testing machine. Met Mater Int 23:736–744. https://doi.org/10.1007/s12540-017-6703-z10.1007/s12540-017-6703-z ↗
15. Lemaignan C, Motta AT (2006) Zirconium alloys in nuclear applications. Mater Sci Technol. https://doi.org/10.1002/9783527603978.mst011110.1002/9783527603978.mst0111 ↗
16. Manahan MP, Argon AS, Harling OK (1981) The development of miniaturized disk bend test for the determination of post irradiation mechanical properties. J Nucl Mater 104:1545–1550. https://doi.org/10.1016/0022-3115(82)90820-010.1016/0022-3115(82)90820-0 ↗
17. Meyers DE, Chen FC, Zhang J, Ardell AJ (1993) Optimization of test parameters for quantitative stress measurements using the miniaturized disk-bend test. J Test Eval 21:263–271. https://doi.org/10.1520/JTE11951J10.1520/JTE11951J ↗
18. Narayana Murty T, Singh RN, Ståhle P (2019) Delayed hydride cracking of Zr–2.5%Nb pressure tube material due to partially constrained precipitates. J Nucl Mater 513(2019):129–142. https://doi.org/10.1016/j.jnucmat.2018.10.04010.1016/j.jnucmat.2018.10.040 ↗
19. Pan ZL, Ritchie IG, Puls MP (1996) The terminal solid solubility of hydrogen and deuterium in Zr–2.5 Nb alloys. J Nucl Mater 228:227–237. https://doi.org/10.1016/S0022-3115(95)00217-010.1016/S0022-3115(95)00217-0 ↗
20. Shah PK, Satheesh PM, Singh RN, Dubey JS, Shriwastaw RS, Balakrishnan KS, Kulkarni AP, Mishra P, Jathar VP, Majumdar S, Alur VD, Anantharaman S, Chakravartty JK (2011) Anisotropy in impact behavior of Zr–2.5Nb pressure tube alloy. Trans Indian Inst Met 64:67–70. https://doi.org/10.1007/s12666-011-0013-910.1007/s12666-011-0013-9 ↗
21. Sharma RK, Sunil S, Kumawat BK, Singh RN, Tewari A, Kashyap BP (2017) Influence of hydride orientation on fracture toughness of CWSR Zr–2.5% Nb pressure tube material between RT and 300 °C. J Nucl Mater 488:231–244. https://doi.org/10.1016/j.jnucmat.2017.03.02510.1016/j.jnucmat.2017.03.025 ↗
22. Sharma RK, Bind AK, Avinash G, Singh RN, Tewari A, Kashyap BP (2018) Effect of radial hydride fraction on fracture toughness of CWSR Zr–2.5% Nb pressure tube material between ambient and 300 °C temperatures. J Nucl Mater 508:546–55510.1016/j.jnucmat.2018.06.003 ↗
23. Singh RN, Kishore R, Mukherjee S, Roychowdhury S, Srivastava D, Sinha TK, De PK, Banerjee S, Kameswaran R, Sheelvantra Smita S, Gopalan B (2003) Hydrogen charging, hydrogen content analysis and metallographic examination of hydride in Zirconium alloys. BARC Report, BARC/2003/E/034
24. Singh RN, Mukherjee S, Gupta A, Banerjee S (2005a) Terminal solid solubility of hydrogen in Zr-alloy pressure tube materials. J Alloys Compd 389:102–112. https://doi.org/10.1016/j.jallcom.2004.07.04810.1016/j.jallcom.2004.07.048 ↗
25. Singh RN, Mukherjee S, Kishore R, Kashyap BP (2005b) Flow behaviour of a modified Zr–2.5 wt%Nb pressure tube alloy. J Nucl Mater 345:146–161. https://doi.org/10.1016/j.jnucmat.2005.05.00810.1016/j.jnucmat.2005.05.008 ↗
26. Singh RN, Lala MR, Dey GK, Sah DN, Batra IS, Ståhle P (2006) Influence of temperature on threshold stress for reorientation of hydrides and residual stress variation across thickness of Zr–2.5Nb alloy pressure tube. J Nucl Mater 359:208–219. https://doi.org/10.1016/j.jnucmat.2006.09.00410.1016/j.jnucmat.2006.09.004 ↗
27. Singh RN, Viswanathan UK, Kumar S, Satheesh PM, Anantharaman S, Chakravartty JK, Ståhle P (2011) Influence of hydrogen content on impact toughness of Zr–2.5 Nb pressure tube alloy. Nucl Eng Des 241:2425–2436. https://doi.org/10.1016/j.nucengdes.2011.04.02410.1016/j.nucengdes.2011.04.024 ↗
28. Singh RN, Bind AK, Srinivasan NS, Ståhle P (2013a) Influence of hydrogen content on fracture toughness of CWSR Zr–2.5 Nb pressure tube alloy. J Nucl Mater 432:87–93. https://doi.org/10.1016/j.jnucmat.2012.07.04610.1016/j.jnucmat.2012.07.046 ↗
29. Singh RN, Khandelwal HK, Bind AK, Sunil S, Stahle P (2013b) Influence of stress field of expanding and contracting plate shaped precipitate on hydride embrittlement of Zr-alloys. Mater Sci Eng A 579:157–163. https://doi.org/10.1016/j.msea.2013.04.11710.1016/j.msea.2013.04.117 ↗
30. Singh RN, Bind AK, Khandelwal HK, Rath BN, Sunil S, Stahle P (2015) Effect of direction of approach of test temperature on fracture toughness of Zr–2.5Nb pressure tube material. Mater Sci Eng A 621:190–197. https://doi.org/10.1016/j.msea.2014.10.05210.1016/j.msea.2014.10.052 ↗
31. Uehira A, Ukai S (2004) Empirical correlation of specimen size effects in Charpy impact properties of 11Cr–0.5 Mo-2W, V, Nb ferritic-martensitic stainless steel. J Nucl Sci Technol 41:973–980. https://doi.org/10.1080/18811248.2004.972632010.1080/18811248.2004.9726320 ↗
32. Viswanathan UK, Singh RN, Basak CB, Anantharaman S, Sahoo KC (2006) Evaluation of effect of hydrogen on toughness of Zircaloy-2 by instrumented drop weight impact testing. J Nucl Mater 350:310–319. https://doi.org/10.1016/j.jnucmat.2006.01.01610.1016/j.jnucmat.2006.01.016 ↗