| Performance of iron–chromium–aluminum alloy surface coatings on Zircaloy 2 under high-temperature steam and normal BWR operating conditions W Zhong, PA Mouche, X Han, BJ Heuser, KK Mandapaka, GS Was Journal of Nuclear Materials 470, 327-338, 2016 | 100 | 2016 |
| Response of Cr and Cr-Al coatings on Zircaloy-2 to high temperature steam W Zhong, PA Mouche, BJ Heuser Journal of Nuclear Materials 498, 137-148, 2018 | 95 | 2018 |
| Effects of carbonitrides and carbides on microstructure and properties of castable nanostructured alloys L Tan, T Graening, X Hu, W Zhong, Y Yang, SJ Zinkle, Y Katoh Journal of Nuclear Materials 540, 152376, 2020 | 22 | 2020 |
| Diffusion-mediated chemical concentration variation and void evolution in ion-irradiated NiCoFeCr high-entropy alloy Z Fan, W Zhong, K Jin, H Bei, YN Osetsky, Y Zhang Journal of Materials Research 36, 298-310, 2021 | 17 | 2021 |
| Clarification of creep deformation mechanism in heat-affected zone of 9Cr steels with In Situ experiments Y Wang, W Zhang, H Huang, Y Wang, W Zhong, J Chen, Z Feng Scripta Materialia 194, 113640, 2021 | 16 | 2021 |
| Microstructure, hardness, and residual stress of the dissimilar metal weldments of SA508-309L/308L-304L W Zhong, JL Lin, Y Chen, Z Li, K An, BJ Sutton, BJ Heuser Metallurgical and Materials Transactions A 52, 1927-1938, 2021 | 15 | 2021 |
| Microstructures and mechanical properties of a modified 9Cr ferritic-martensitic steel in the as-built condition after additive manufacturing W Zhong, N Sridharan, D Isheim, KG Field, Y Yang, K Terrani, L Tan Journal of Nuclear Materials 545, 152742, 2021 | 15 | 2021 |
| TEM/STEM study of Zircaloy-2 with protective FeAl (Cr) layers under simulated BWR environment and high-temperature steam exposure D Park, PA Mouche, W Zhong, KK Mandapaka, GS Was, BJ Heuser Journal of Nuclear Materials 502, 95-105, 2018 | 15 | 2018 |
| Microstructural stability of tantalum-alloyed ferritic-martensitic steel with neutron irradiation to 7.4 dpa at~ 490 C L Tan, W Zhong, T Chen Materialia 9, 100608, 2020 | 13 | 2020 |
| Azimuthally anisotropic hydride lens structures in Zircaloy 4 nuclear fuel cladding: High-resolution neutron radiography imaging and BISON finite element analysis JL Lin, W Zhong, HZ Bilheux, BJ Heuser Journal of Nuclear Materials 496, 129-139, 2017 | 11 | 2017 |
| Tailoring microstructure in sintered Cu-Cr-Nb-Zr alloys for fusion components B Cheng, L Wang, DJ Sprouster, JR Trelewicz, W Zhong, Y Yang, ... Journal of Nuclear Materials 551, 152956, 2021 | 7 | 2021 |
| The challenge of acquiring a satisfactory EBSD result of CWSR Zircaloy‐4 cladding tube KC LAN, W Zhong, PA Mouche, HM TUNG, H Lee, BJ Heuser, ... Journal of Microscopy 272 (1), 25-34, 2018 | 6 | 2018 |
| Effects of sample bias on adhesion of magnetron sputtered Cr coatings on SiC PA Mouche, A Evans, W Zhong, T Koyanagi, Y Katoh Journal of Nuclear Materials 556, 153251, 2021 | 5 | 2021 |
| Microstructure and mechanical properties of high Mn-containing ferritic-martensitic alloys exposed to cyclical thermal treatment W Zhong, Y Yang, KG Field, N Sridharan, K Terrani, L Tan Materials Science and Engineering: A 813, 141143, 2021 | 4 | 2021 |
| Modified microstructures in proton irradiated dual phase 308L weldment filler material Z Li, X Zhan, XM Bai, SC Lee, W Zhong, BJ Sutton, BJ Heuser Journal of Nuclear Materials 548, 152825, 2021 | 4 | 2021 |
| Deciphering the multiple deformation mechanisms responsible for sustained work hardening in a FeCrCoNi medium entropy alloy W Zhong, Y Yang, S Hayakawa, H Xu, K An, I Stinson, A Borisevich, ... International Journal of Plasticity 167 (1), 2023 | 3 | 2023 |
| Effects of helium on irradiation response of reduced-activation ferritic-martensitic steels: using nickel isotopes to simulate fusion neutron response BK Kim, L Tan, H Sakasegawa, CM Parish, W Zhong, H Tanigawa, ... Journal of Nuclear Materials 545, 152634, 2021 | 3 | 2021 |
| Radiological analysis and transmutation calculation of representative castable nanostructured alloys W Zhong, L Tan Fusion Engineering and Design 160, 111899, 2020 | 3 | 2020 |
| Neutron irradiation induced defects and clustering in NF616 and T91 W Zhong, TA Saleh, L Tan Journal of Nuclear Materials 552, 153001, 2021 | 2 | 2021 |
| Post-Irradiation-Examination of the ORNL and LANL Samples W Zhong, L Tan, K Linton, TA Saleh Oak Ridge National Lab.(ORNL), Oak Ridge, TN (United States), 2019 | 2 | 2019 |
Brent HeuserProfessor of Nuclear Engineering, University of IllinoisVerified email at illinois.edu
