PSI - Issue 60

Rishi K Sharma et al. / Procedia Structural Integrity 60 (2024) 264–276 Rishi K. Sharma/ Structural Integrity Procedia 00 (2019) 000 – 000

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of hydrogen and reorienting the hydrides in the radial direction and then subjecting it to an aggressive contaminant by bubbling an air through HCl in the PT-CT annulus of the test spool. Following are major outcome from the experiments: a) In absence of crack initiation at notch locations, only one notch gets opened up and remaining three were found to be unaffected. b) The crack in the pressure tube spool became through thickness at comparatively lower pressure in presence of radial hydrides in comparison to as received material and also with circumferential hydrides. The length of extension of opened notch was found to be more in presence of radial hydrides. c) Multiple opening of pressure tube was observed when it was allowed for crack initiation before bursting by subjecting the spool to corrosive environment & with radial hydrides. Acknowledgements Authors are grateful the Shri S K Mahajan and team members of experimental test facility at R&D center, NPCIL, Tarapur for their invaluable support. Constant encouragement provided by Mr. A. K. Balasubramanian, former Director (T), NPCIL is acknowledged. Technical assistance provided by Mr. S. A. Chandanshive and Mr. Pramod N. Madavkar of MMD, BARC in hydrogen charging is acknowledged. Coleman, C., & Hardie, D. (1966). The Hydrogen embrittlement of alpha-Zirconium - A review. Journal of the less common metals, 11 , 168-185. Gopalan, A., Bind, A. K., Sunil, S., Murty, T. N., Sharma, R. K., Samanta, A., . . . Singh, R. N. (2021). Effect of radial hydride on room temperature fracture toughness of Zr-2.5Nb pressure tube material. Journal of Nuclear Materials 544 , 152681. Holt, R., Christodoulou, N., & Causey, A. (2003). Anisotropy of in-reactor deformation of Zr – 2.5Nb pressure tubes. Journal of Nuclear Materials 317(2-3) , 256-260. Moan, G., Coleman, C., Price, E., Rodgers, D., & Sagat, S. (1990). Leak before break in the Pressure Tubes of CANDU Reactors. International Journal of Pressure Vessel & Piping 43 , 1-21. Motta, A. T., Capolungo, L., Chen, L., Cinbiz, N. M., Daymond, M. R., Koss, D. A., . . . Zirky, M. A. (2019). Hydrogen in Zirconium alloys: A review. Journal of Nuclear Materials, 518 , 440-460. Muktibodh, U. C., Dixit, K. B., Ingole, S. M., & Prakash, B. (2016). Design of Indian Pressurized Heavy Water Reactors. Global Applications of the ASME Boiler and Pressure Vessel Code , 16.1-16.25. Murty, T. N., Singh, R. N., & Ståhle, P. (2019). Delayed hydride cracking of Zr-2.5%Nb pressure tube material due to partially constrained precipitates. Journal of Nuclear Materials 513 , 129-142. Northwood, D., & Kosasih, U. (1983). Hydrides and Delayed Hydrogen Cracking in Zirconium and its Alloys. International Metals Reviews 28(2) , 92-121. Nouduru, S. K., Kiran, M. K., S., R., Gumma, S., Sharma, R. K., Verma, R., & Kain, V. (2021). Nodular corrosion of zirconium alloys in gaseous environment containing different contaminants. Journal of Nuclear Materials 545 , 152640. Rodgers, D., Coleman, C., Griffiths, M., Bickel, G., Theaker, J., Muir, I., . . . Levi, M. R. (2008). In-reactor performance of pressure tubes in CANDU reactors. Journal of Nuclear Materials, 383(1-2) , 22-27. Sharma, R. K., Bind, A., Avinash, G., Singh, R., Tewari, A., & Kashyap, B. (2018). Effect of radial hydride fraction on fracture toughness of CWSR Zr-2.5%Nb pressure tube material between ambient and 300 °C temperatures. Journal of Nuclear Materials 508 , 546-555. Sharma, R. K., Sunil, S., Kumawat, B., Singh, R., Tewari, A., & Kashyap, B. (2017). Influence of hydride orientation on fracture toughness of CWSR Zr-2.5%Nb pressure tube material between RT and 300 °C . Journal of Nuclear Materials 488 , 231-244. Sharma, R. K., Tewari, A., Singh, R., & Kashyap, B. (2018). Optimum shape and orientation of δ - hydride precipitate in α -zirconium matrix for different temperatures. Journal of Alloys and Compounds 742 , 804-813. Singh, R. N., Kishore, R., Sinha, T. K., Banerjee, S., & Kashyap, B. P. (2003). Stress field estimation around a semi-constrained inclusion and its validation by interpreting hydride platelet orientation around a blister in a Zr-2.5Nb alloy. Materials Science and Engineering A339 , 17-28. Singh, R., Kishore, R., Mukherjee, S., Roychowdhury, S., Srivastava, D., Sinha, T., . . . Banerjee, S. (2003). Hydrogen Charging, Hydrogen Content Analysis and Metallographic Examination of Hydride in Zirconium Alloys. BARC report E034 . Singh, R., Kishore, R., Singh, S., Sinha, T., & Kashyap, B. (2004). Stress-reorientation of hydrides and hydride embrittlement of Zr – 2.5 wt% Nb References Bajaj, S. S., & Gore, A. R. (2006). The Indian PHWR. Nuclear Engineering and Design, 236 , 701-722. Bind, A. K., Avinash, G., Sunil, S., Sharma, R. K., & Singh, R. N. (2023). Effect of radial hydrides on fracture behavior of Zr-2.5Nb pressure tube material. Journal of Nuclear Materials .