On the use of SRIM for calculating vacancy production: Quick calculation and full-cascade options S Agarwal, Y Lin, C Li, RE Stoller, SJ Zinkle Nuclear Instruments and Methods in Physics Research Section B: Beam …, 2021 | 111 | 2021 |
Toward accurate evaluation of bulk hardness from nanoindentation testing at low indent depths P Zhu, Y Zhao, S Agarwal, J Henry, SJ Zinkle Materials & Design 213, 110317, 2022 | 56 | 2022 |
A review on helium mobility in inorganic materials P Trocellier, S Agarwal, S Miro Joural of Nuclear Materials 445 (1-3), 128-142, 2014 | 50 | 2014 |
Neutron irradiation-induced microstructure damage in ultra-high temperature ceramic TiC S Agarwal, T Koyanagi, A Bhattacharya, L Wang, Y Katoh, X Hu, M Pagan, ... Acta materialia 186, 1-10, 2020 | 45 | 2020 |
Helium induced microstructure damage, nano-scale grain formation and helium retention behaviour of ZrC S Agarwal, A Bhattacharya, P Trocellier, SJ Zinkle Acta Materialia 163, 14-27, 2019 | 41 | 2019 |
Multiscale characterization of irradiation behaviour of ion-irradiated SiC/SiC composites S Agarwal, G Duscher, Y Zhao, ML Crespillo, Y Katoh, WJ Weber Acta Materialia 161, 207-220, 2018 | 40 | 2018 |
Evolution of the microstructural and mechanical properties of BAM-11 bulk metallic glass during ion irradiation and annealing J Brechtl, S Agarwal, ML Crespillo, T Yang, H Bei, SJ Zinkle Journal of Nuclear Materials 523, 299-309, 2019 | 36 | 2019 |
Revealing irradiation damage along with the entire damage range in ion-irradiated SiC/SiC composites using Raman spectroscopy S Agarwal, Q Chen, T Koyanagi, Y Zhao, SJ Zinkle, WJ Weber Journal of Nuclear Materials 526, 151778, 2019 | 35 | 2019 |
Helium mobility in advanced nuclear ceramics S Agarwal, P Trocellier, Y Serruys, S Vaubaillon, S Miro Nuclear Instruments and Methods in Physics Research Section B: Beam …, 2014 | 29 | 2014 |
An experimental study of helium diffusion and helium induced microstructural evolution in ion implanted polycrystalline titanium nitride S Agarwal, P Trocellier, D Brimbal, S Vaubaillon Acta Materialia 121, 1-14, 2016 | 17 | 2016 |
Study of helium migration in nuclear materials at Jannus–Saclay P Trocellier, S Miro, Y Serruys, S Vaubaillon, S Pellegrino, S Agarwal, ... Nuclear Instruments and Methods in Physics Research Section B: Beam …, 2015 | 16 | 2015 |
Diffusion and retention of helium in titanium carbide S Agarwal, P Trocellier, S Vaubaillon, S Miro Journal of Nuclear Materials 448 (1-3), 144-152, 2014 | 16 | 2014 |
Investigation of the mechanical and microstructural evolution of a Cu based bulk metallic glass during ion irradiation J Brechtl, S Agarwal, ML Crespillo, J Salasin, T Yang, H Bei, SJ Zinkle Intermetallics 116, 106655, 2020 | 15 | 2020 |
The mechanism behind the high radiation tolerance of Fe–Cr alloys S Agarwal, M Butterling, MO Liedke, KH Yano, DK Schreiber, ACL Jones, ... Journal of Applied Physics 131 (12), 2022 | 9 | 2022 |
Application of a deep learning semantic segmentation model to helium bubbles and voids in nuclear materials S Agarwal, A Sawant, M Faisal, SE Copp, J Reyes-Zacarias, YR Lin, ... Engineering Applications of Artificial Intelligence 126, 106747, 2023 | 6 | 2023 |
Experimental studies on primary damage formation S Agarwal, SJ Zinkle Elsevier, 2020 | 6 | 2020 |
Effects of irradiation spectrum on the microstructural and mechanical properties of bulk metallic glasses J Brechtl, ML Crespillo, S Agarwal, H Bei, SJ Zinkle Journal of Nuclear Materials 533, 152084, 2020 | 5 | 2020 |
Challenges to accurate evaluation of bulk hardness from nanoindentation testing at low indent depths P Zhu, Y Zhao, S Agarwal, J Hay, J Henry, S Zinkle Available at SSRN 3793936, 2021 | 4 | 2021 |
An exploratory study on helium mobility in amorphous and crystallized bulk metallic glasses J Brechtl, S Agarwal, X Hu, D Chen, M Chancey, H Bei, YQ Wang, ... Journal of Nuclear Materials 543, 152617, 2021 | 4 | 2021 |
Comparison of hardening and microstructures of ferritic/martensitic steels irradiated with fast neutrons and dual ions P Zhu, YR Lin, S Agarwal, V Pauly, S Taller, SJ Zinkle Journal of Nuclear Materials, 155211, 2024 | 3 | 2024 |