PSI - Issue 71

Priti Kotak Shah et al. / Procedia Structural Integrity 71 (2025) 271–278

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58 60 62 64 66 68 70 72 74 76

Modulus Value (GPa)

As-fab HydRim1

HydRim2

HydUni1

HydUni2

HydUni3

Condition of Clad Tube

Fig.17. Bar chart showing variation of modulus value for different clad specimens

4. Conclusions RTT: i. There is no change in mechanical properties for the clad tubes with rimmed hydrides. ii. Upto 400 wppm hydrogen content, there is not much change in elongation. Thereafter, break Strain decreases as we increase the hydrogen content of the uniformly hydrided clad tubes. iii. Both Yield Strength and UTS of severely hydrided (1200 ppm) clad tube come out to be higher compared to the mildly hydride or as fabricated clads. RCT: i. There is no change in mechanical properties for the clad tubes with rimmed hydrides studied. ii. Beyond 400 wppm hydrogen, both total deflection and plastic deflection decrease with increase in hydrogen content of the homogenised clad tubes. iii. Area under the curve upto maximum load decreases significantly with increase in hydrogen content of the clad tubes. iv. Modulus value remains almost constant with change in hydride concentration. Acknowledgements The authors would like to thank Shri H. N Tripathi, Nirav Kumar for their help in carrying out hydriding and the experiments. Billone M. C., 2015. Ductility Determination using Ring-Compression Tests. NRC Public Meeting Draft Regulatory Guides DG-1261, 1262, and 1263. Oak Ridge National Laboratory, April 29-30, 2015. Chatterjee, S., Anantharaman, S., Balakrishnan, K.S., Sivaramkrishnan, K.S., Ring Tensile testing of irradiated clad materials. BARC/I-643,1981 Frolov, A. S., Fedotov, I.V., Gurovich, B.A., 2021. Evaluation of the true-strength characteristics for isotropic materials using ring tensile test. Nuclear Engineering and Technology 53, 7. 2323-2333 Garrison, B. E., 2018. Failure Properties and Phenomena for Zircaloy-4 from Ring Compression Testing. Master's Thesis, University of Tennessee. https://trace.tennessee.edu/utk_gradthes/5386 Martin-Rengel, M. A., Gómez Sánchez, F.J., Ruiz-Hervías, J., Caballero, L., 2013. Determination of the hoop fracture properties of unirradiated hydrogen-charged nuclear fuel cladding from ring compression tests. Journal of Nuclear Materials 436, 1 – 3. 123-129 Shriwastaw, R. S., Sawarn, T. K., Banerjee, S., Rath, B. N., Dubey, J. S., Kumar, S., Singh, J. L., Bhasin, V., 2017. Estimation of ring tensile properties of steam oxidized Zircaloy-4 fuel cladding under simulated LOCA condition. Journal of Nuclear Materials 493. 460-470 Suman, S., Khan, M. K., Pathak, M., Singh, R. N., 2017. Effects of Hydride on Crack Propagation in Zircaloy-4. Procedia Engineering 173, 1185-1190. References