Weicheng Zhong
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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
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
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
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
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
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
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
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
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
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
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
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
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
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
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
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
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
Radiological analysis and transmutation calculation of representative castable nanostructured alloys
W Zhong, L Tan
Fusion Engineering and Design 160, 111899, 2020
Neutron irradiation induced defects and clustering in NF616 and T91
W Zhong, TA Saleh, L Tan
Journal of Nuclear Materials 552, 153001, 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
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Articles 1–20