"Characterization of neutron-irradiated HT-UPS steel by high-energy X-ray diffraction microscopy"
Xuan Zhang, Jun-Sang Park, Jonathan Almer, Meimei Li,
Journal of Nuclear Materials
Vol. 471
2016
280-288
Link
This paper presents the first measurement of neutron-irradiated microstructure using far-field high-energy X-ray diffraction microscopy (FF-HEDM) in a high-temperature ultrafine-precipitate-strengthened (HT-UPS) austenitic stainless steel. Grain center of mass, grain size distribution, crystallographic orientation (texture), diffraction spot broadening and lattice constant distributions of individual grains were obtained for samples in three different conditions: non-irradiated, neutron-irradiated (3dpa/500 °C), and irradiated + annealed (3dpa/500 °C + 600 °C/1 h). It was found that irradiation caused significant increase in grain-level diffraction spot broadening, modified the texture, reduced the grain-averaged lattice constant, but had nearly no effect on the average grain size and grain size distribution, as well as the grain size-dependent lattice constant variations. Post-irradiation annealing largely reversed the irradiation effects on texture and average lattice constant, but inadequately restored the microstrain. |
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"Effects of neutron irradiation and post-irradiation annealing on the microstructure of HT-UPS stainless steel"
Chi Xu, Wei-Ying Chen, Xuan Zhang, Meimei Li, Yong Yang, Yaqiao Wu,
Journal of Nuclear Materials
Vol. 507
2018
188-197
Link
Microstructural changes resulted from neutron irradiation and post-irradiation annealing in a high-temperature ultra-fine precipitate strengthened (HT-UPS) stainless steel were characterized using transmission electron microscopy (TEM) and atom probe tomography (APT). Three HT-UPS samples were neutron-irradiated to 3 dpa at 500?°C, and after irradiation, two of them were annealed for 1?h?at 600?°C and 700?°C, respectively. Frank dislocation loops were the dominant defect structure in both the as-irradiated and 600?°C post-irradiation-annealed (PIAed) samples, and the loop sizes and densities were similar in these two samples. Unfaulted dislocation loops were observed in the 700?°C PIAed sample, and the loop density was greatly reduced in comparison with that in the as-irradiated sample. Nano-sized MX precipitates were observed under TEM in the 700?°C PIAed sample, but not in the 600?°C PIAed or the as-irradiated samples. The titanium-rich clusters were identified in all three samples using APT. The post-irradiation annealing (PIA) caused the growth of the Ti-rich clusters with a stronger effect at 700?°C than at 600?°C. The irradiation caused elemental segregations at the grain boundary and the grain interior, and the grain boundary segregation behavior is consistent with observations in other irradiated austenitic steels. APT results showed that PIA reduced the magnitude of irradiation induced segregations. |
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"High-energy synchrotron x-ray techniques for studying irradiated materials"
David Hoelzer, Jun-Sang Park, Xuan Zhang, Hemant Sharma, Peter Kenesei, Meimei Li, Jonathan Almer,
Journal of Materials Research
Vol. 30
2015
1380-1391
Link
High performance materials that can withstand radiation, heat, multiaxial stresses, and corrosive environment are necessary for the deployment of advanced nuclear energy systems. Nondestructive in situ experimental techniques utilizing high energy x-rays from synchrotron sources can be an attractive set of tools for engineers and scientists to investigate the structure-processing-property relationship systematically at smaller length scales and help build better material models. In this study, two unique and interconnected experimental techniques, namely, simultaneous small-angle/wide-angle x-ray scattering (SAXS/WAXS) and far-field high-energy diffraction microscopy (FF-HEDM) are presented. The changes in material state as Fe-based alloys are heated to high temperatures or subject to irradiation are examined using these techniques.
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"High-energy x-ray diffraction microscopy study of deformation microstructures in neutron-irradiated polycrystalline Fe-9%Cr, "
Xuan Zhang, Meimei Li, Jun-Sang Park, Peter Kenesei, Hemant Sharma, Jonathan Almer,
Journal of Nuclear Materials
Vol. 508
2018
556-566
Link
In this study, we used far-field high-energy x-ray diffraction microscopy (FF-HEDM) to measure in 3D the spatial distributions of the sizes, orientations, and residual strains of grains and subgrains formed by room-temperature tensile deformation in a neutron-irradiated (450?°C, 0.01dpa) Fe-9Cr specimen and its unirradiated counterpart. We found that neutron irradiation under this condition alone had no effect on the grain size distribution. After deformation, grains fragmented into subgrains in both unirradiated and irradiated specimens: the irradiated specimen contained a few large subgrains which co-existed with many smaller subgrains, while the unirradiated specimen contained small subgrains with a relatively uniform size distribution. Prior to deformation, the irradiated specimen had higher residual strain spread compared to its unirradiated counterpart, while after deformation to the maximum uniform elongation, the strain distributions among subgrains were similar between the unirradiated and irradiated specimens. The FF-HEDM measurements provide new insight into the effects of neutron irradiation on the mechanical response of Fe-Cr ferritic alloys. |
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"In situ high-energy X-ray diffraction study of tensile deformation of neutron-irradiated polycrystalline Fe-9%Cr alloy"
Meimei Li, James Stubbins, Chi Xu, Xuan Zhang, Jun-Sang Park, Peter Kenesei, Jonathan Almer,
Acta Materialia
Vol. 126
2017
67-76
Link
The effect of neutron irradiation on tensile deformation of a Fe-9wt%Cr alloy was investigated using in situ high-energy synchrotron X-ray diffraction during room-temperature uniaxial tension tests. New insights into the deformation mechanisms were obtained through the measurements of lattice strain evolution and the analysis of diffraction peak broadening using the modified Williamson-Hall method. Two neutron-irradiated specimens, one irradiated at 300 °C to 0.01 dpa and the other at 450 °C to 0.01 dpa, were tested along with an unirradiated specimen. The macroscopic stress–strain curves of the irradiated specimens showed increased strength, reduced ductility and reduced work-hardening exponent compared to the unirradiated specimen. The evolutions of the lattice strain, the dislocation density and the coherent scattering domain size in the deformation process revealed different roles of the submicroscopic defects in the 300 °C/0.01 dpa specimen and the nanometer-sized dislocation loops in the 450 °C/0.01 dpa specimen; the dislocation loops were more effective in dislocation pinning. While the work hardening rate of stage II was unaffected by irradiation, significant dynamic recovery in stage III in the irradiated specimens led to the early onset of necking without stage IV as observed in the unirradiated specimen. |
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"In-situ high-energy X-ray characterization of neutron irradiated HT-UPS stainless steel under tensile deformation"
Chi Xu, Xuan Zhang, Yiren Chen, Meimei Li, Jun-Sang Park, Peter Kenesei, Jason Almer, Yong Yang,
Acta Materialia
Vol. 156
2018
330-341
Link
The tensile deformation behavior of a high-temperature, ultrafine-precipitate strengthened (HT-UPS) stainless steel was characterized in-situ with high-energy X-ray diffraction at 20 and 400?°C. The HT-UPS samples were neutron irradiated to 3 dpa at 400?°C. Significant irradiation hardening and ductility loss were observed at both temperatures. Lattice strain evolutions of the irradiated samples showed a strong linear response up to near the onset of the macroscopic yield, in contrast to the unirradiated HT-UPS which showed a pronounced non-linear behavior well below the macroscopic yield. While the room-temperature diffraction elastic moduli in the longitudinal direction increased after irradiation, the 400?°C moduli were similar before and after irradiation. The evolution of the {200} lattice strain parallel to the loading axis () showed unique characteristics: in the plastic regime, the evolution of after yield is temperature-dependent in the unirradiated specimens but temperature-independent in the irradiated specimens; and the value of at the yield is an irradiation-sensitive, temperature-independent parameter. The evolution of corresponds well with the dislocation density evolution, and is an effective probe of the deformation-induced long-range internal stresses in the HT-UPS steel. |
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"Microstructural evolution of NF709 (20Cr–25Ni–1.5 MoNbTiN) under neutron irradiation"
Bong Goo Kim, Lizhen Tan, Yong Yang, Cheryl Xu, Xuan Zhang, Meimei Li,
Journal of Nuclear Materials
Vol. 470
2016
229-235
Link
Because of its superior creep and corrosion resistance as compared with general austenitic stainless steels, NF709 has emerged as a candidate structural material for advanced nuclear reactors. To obtain fundamental information about the radiation resistance of this material, this study examined the microstructural evolution of NF709 subjected to neutron irradiation to 3 displacements per atom at 500 °C. Transmission electron microscopy, scanning electron microscopy, and high-energy x-ray diffraction were employed to characterize radiation-induced segregation, Frank loops, voids, as well as the formation and reduction of precipitates. Radiation hardening of ∼76% was estimated by nanoindentation, approximately consistent with the calculation according to the dispersed barrier-hardening model, suggesting Frank loops as the primary hardening source. |
"In-Situ Synchrotron X-Ray Scattering Study on the Tensile Properties of Neutron Irradiated Ferritic/ Martensitic Alloys" Xiang Liu, Kuan-Che Lan, Meimei Li, Xuan Zhang, Chi Xu, James Stubbins, ANS Annual Meeting 2018 June 11-22, (2018) |
DOE Awards 33 Rapid Turnaround Experiment Research Proposals - Projects total approximately $1.2 million These projects will continue to advance the understanding of irradiation effects in nuclear fuels and materials in support of the mission of the DOE Office of Nuclear Energy. Monday, June 18, 2018 - Calls and Awards |
RTE 2nd Call Awards Announced - Projects total approximately $1.6 million These project awards went to principal investigators from 26 U.S. universities, eight national laboratories, two British universities, and one Canadian laboratory. Tuesday, May 14, 2019 - Calls and Awards |
"Effect of irradiation-induced strength anisotropy on the reorientation trajectories and fragmentation behavior of grains in BCC polycrystals under tensile loading" Dominic Piedmont, Mark C. Messner, Meimei Li, James Stubbins, Jun-Sang Park, Xuan Zhang, Matthew Kasemer, Ezra Mengiste, [2024] Acta Materialia · DOI: 10.1016/j.actamat.2023.119503 · EID: 2-s2.0-85177184135 · ISSN: 1359-6454 | |
"The role of Ca on the microstructure and tensile properties of Mg-Al-Zn-Ca alloys" Gaoming Zhu, Jun-Sang Park, Xuan Zhang, Zhe Song, Huamiao Wang, Xiaoqin Zeng, Leyun Wang, Yunhao Fan, [2023] Materialia · DOI: 10.1016/j.mtla.2023.101787 · EID: 2-s2.0-85159197436 · ISSN: 2589-1529 | |
"Tomo2Mesh: Fast Porosity Mapping and Visualization for Synchrotron Tomography" Viktor Nikitin, Yashas Satapathy, Zhengchun Liu, Xuan Zhang, Peter Kenesei, Weijian Zheng, Francesco De Carlo, Ian Foster, Rajkumar Kettimuthu, Aniket Tekawade, [2023] Proceedings 2023 IEEE 19th International Conference on e-Science, e-Science 2023 · DOI: 10.1109/e-science58273.2023.10254907 · EID: 2-s2.0-85174274147 | |
"Understanding creep behaviors of additively manufactured 316L stainless steel via void characterization" Christopher P. Carter, Yashas Satapathy, Aniket Tekawade, Jun-Sang Park, Peter Kenesei, Meimei Li, Xuan Zhang, [2023] Materials Research Letters · DOI: 10.1080/21663831.2023.2244969 · EID: 2-s2.0-85169664044 · ISSN: 2166-3831 | |
"Developing ductile and isotropic Ti alloy with tailored composition for laser powder bed fusion" Zhe Song, Xuan Zhang, Jun-Sang Park, Jonathan Almer, Gaoming Zhu, Yiwen Chen, Quan Li, Xiaoqin Zeng, Yanjun Li, Leyun Wang, [2022] Additive Manufacturing · DOI: 10.1016/j.addma.2022.102656 · EID: 2-s2.0-85124120587 · ISSN: 2214-8604 | |
"Effect of heat treatment on creep behavior of 316 L stainless steel manufactured by laser powder bed fusion" Wei-Ying Chen, Xuan Zhang, Meimei Li, [2022] Journal of Nuclear Materials · DOI: 10.1016/j.jnucmat.2021.153469 · EID: 2-s2.0-85121621688 · ISSN: 0022-3115 | |
"In-situ High-energy X-ray Diffraction Study on Deformation Behavior of Neutron-Irradiated Fe-9%Cr" [2022] Transactions of the American Nuclear Society · DOI: 10.13182/t126-38282 · EID: 2-s2.0-85180620391 · ISSN: 0003-018X | |
"Phase stability, mechanical properties, and ion irradiation effects in face-centered cubic CrFeMnNi compositionally complex solid-solution alloys at high temperatures" Michael Moorehead, Mohamed Elbakhshwan, Xuan Zhang, Pengyuan Xiu, Lingfeng He, Mukesh Bachhav, Kumar Sridharan, Adrien Couet, Calvin Parkin, [2022] Journal of Nuclear Materials · DOI: 10.1016/j.jnucmat.2022.153733 · EID: 2-s2.0-85129338965 · ISSN: 0022-3115 | |
"Real-time porosity mapping and visualization for synchrotron tomography"
Aniket Tekawade, Viktor Nikitin, Yashas Satapathy, Zhengchun Liu, Xuan Zhang, Peter Kenesei, Francesco De Carlo, Rajkumar Kettimuthu, Ian Foster,
[2022]
TechRxiv
· DOI: 10.36227/techrxiv.20369421
· EID: 2-s2.0-85136188638
<p>Applications of X-ray computed tomography (CT) for porosity characterization of engineering materials often involve an extended data analysis workflow that includes CT reconstruction of raw projection data, binarization, labeling and mesh extraction. It is often desirable to map the porosity in larger samples but the computational challenge of reducing gigabytes of raw data to porosity information poses a critical bottleneck. In this work, we describe algorithms and implementation of an end-to-end porosity mapping code that processes raw projection data from a synchrotron CT instrument into a porosity map and visualization in the form of triangular face mesh. Towards this objective, we report the development of a novel subset reconstruction scheme for X-ray CT using filtered backprojection and a convolutional neural network that allows us to reconstruct arbitrarily-shaped subsets of a tomography object. We build upon this scheme to implement the complete code for porosity mapping. The code first detects possible voids by performing a coarse reconstruction on down-sampled projections and then improves the shape of those voids with higher detail offered by reconstructing selected subsets from the original raw data. We report measurements of the time taken by this code to perform complete processing from raw data to a triangular face mesh for several visualization scenarios on a single highperformance workstation equipped with GPU. We show that we can now visualize local porosity within a 8 gigavoxel CT volume (12 gigabytes raw data) within 1 to 2 minutes and a 64 gigavoxel CT volume (100 gigabytes of raw data) within 3 to 7 minutes.</p> |
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"Unveiling microstructure-property correlations in nuclear materials with high-energy synchrotron X-ray techniques" Xuan Zhang, [2022] Journal of Nuclear Materials · DOI: 10.1016/j.jnucmat.2022.153572 · EID: 2-s2.0-85124037371 · ISSN: 0022-3115 | |
"Creep behavior of 316 L stainless steel manufactured by laser powder bed fusion" Xuan Zhang, Wei-Ying Chen, T.S. Byun, Meimei Li, [2021] Journal of Nuclear Materials · DOI: 10.1016/j.jnucmat.2021.152847 · EID: 2-s2.0-85100438350 · ISSN: 0022-3115 | |
"In situ high-energy X-ray study of deformation mechanisms in additively manufactured 316L stainless steel" Peter Kenesei, Jun-Sang Park, Jonathan Almer, Meimei Li, Xuan Zhang, [2021] Journal of Nuclear Materials · DOI: 10.1016/j.jnucmat.2021.152874 · EID: 2-s2.0-85101143837 · ISSN: 0022-3115 | |
"In-situ ion irradiation study of alloy 709 stainless steels with different processing histories" Wei-Ying Chen, Alexander Caputo, Xuan Zhang, [2021] Journal of Nuclear Materials · DOI: 10.1016/j.jnucmat.2021.153052 · EID: 2-s2.0-85106635165 · ISSN: 0022-3115 | |
"APS: High-Energy X-rays Expediting Applied and Fundamental Research" J. Almer, P. Kenesei, J.-S Park, R. Osborn, Y. Ren, D. Robinson, M. Krogstad, S. Rosenkranz, Xuan Zhang, Meimei Li, K.M. Wiaderek, U. Ruett, [2020] Synchrotron Radiation News · DOI: 10.1080/08940886.2020.1841498 · EID: 2-s2.0-85100061703 · ISSN: 1931-7344 | |
"Creep resistance of additively manufactured 316 stainless steel" W. Chen, F. Heidet, M. Li, K. Terrani, X. Zhang, T. Byun, [2020] Transactions of the American Nuclear Society · DOI: 10.13182/t122-32291 · EID: 2-s2.0-85092142041 · ISSN: 0003-018X | |
"High temperature deformation processes in additively manufactured 316L stainless steel" K. Terrani, T. Byun, W. Chen, X. Zhang, M. Li, F. Heidet, [2020] Transactions of the American Nuclear Society · DOI: 10.13182/t123-32952 · EID: 2-s2.0-85118161032 · ISSN: 0003-018X | |
"High-energy synchrotron x-ray study of deformation-induced martensitic transformation in a neutron-irradiated Type 316 stainless steel" Chi Xu, Yiren Chen, Wei-Ying Chen, Jun-Sang Park, Peter Kenesei, Jonathan Almer, Jatuporn Burns, Yaqiao Wu, Meimei Li, Xuan Zhang, [2020] Acta Materialia · DOI: 10.1016/j.actamat.2020.08.057 · EID: 2-s2.0-85090947638 · ISSN: 1359-6454 | |
"In-situ high-energy X-ray study of deformation mechanisms in additively manufactured 316 stainless steel" P. Kenesei, M. Li, J. Park, X. Zhang, J. Almer, [2020] Transactions of the American Nuclear Society · DOI: 10.13182/t122-32407 · EID: 2-s2.0-85092173139 · ISSN: 0003-018X | |
"Laser powder bed fusion of Inconel 718 on 316 stainless steel" Xuan Zhang, Meimei Li, Ruqing Xu, Cang Zhao, Tao Sun, Wei-Ying Chen, [2020] Additive Manufacturing · DOI: 10.1016/j.addma.2020.101500 · EID: 2-s2.0-85089227380 · ISSN: 2214-8604 | |
"Microstructure and deformation behavior of thermally aged cast austenitic stainless steels" C. Xu, X. Zhang, W.-Y. Chen, J.-S. Park, J. Almer, M. Li, Z. Li, Y. Yang, A. S. Rao, B. Alexandreanu, K. Natesan, Y. Chen, [2019] Minerals, Metals and Materials Series · DOI: 10.1007/978-3-030-04639-2_124 · EID: 2-s2.0-85064061789 · ISSN: 2367-1696 | |
"Effects of neutron irradiation and post-irradiation annealing on the microstructure of HT-UPS stainless steel" Wei-Ying Chen, Xuan Zhang, Yaqiao Wu, Meimei Li, Yong Yang, Chi Xu, [2018] Journal of Nuclear Materials · DOI: 10.1016/j.jnucmat.2018.04.043 · EID: 2-s2.0-85046764331 · ISSN: 0022-3115 | |
"High-energy x-ray diffraction microscopy study of deformation microstructures in neutron-irradiated polycrystalline Fe-9%Cr" Meimei Li, Jun-Sang Park, Peter Kenesei, Hemant Sharma, Jonathan Almer, Xuan Zhang, [2018] Journal of Nuclear Materials · DOI: 10.1016/j.jnucmat.2018.06.004 · EID: 2-s2.0-85048574652 · ISSN: 0022-3115 | |
"In-situ high-energy X-ray characterization of neutron irradiated HT-UPS stainless steel under tensile deformation" Xuan Zhang, Yiren Chen, Meimei Li, Jun-Sang Park, Peter Kenesei, Jonathan Almer, Yong Yang, Chi Xu, [2018] Acta Materialia · DOI: 10.1016/j.actamat.2018.07.008 · EID: 2-s2.0-85049902022 · ISSN: 1359-6454 | |
"In-situ synchrotron x-ray scattering study on the tensile properties of neutron irradiated ferritic/martensitic alloys" [2018] Transactions of the American Nuclear Society · EID: 2-s2.0-85062940352 · ISSN: 0003-018X | |
"Fracture toughness and deformation behavior of cast austenitic stainless steels after thermal aging"
Wei-Ying Chen, Chi Xu, Xuan Zhang, Zhangbo Li, Yong Yang, Appajosula S. Rao, Bogdan Alexandreanu, Krishnamurti Natesan, Yiren Chen,
[2017]
American Society of Mechanical Engineers, Pressure Vessels and Piping Division (Publication) PVP
· DOI: 10.1115/pvp2017-65768
· EID: 2-s2.0-85034062575
· ISSN: 0277-027X
Cast austenitic stainless steels (CASSs) are used in the cooling system of light water reactors (LWRs) for components with complex shapes, such as pump casings, valve bodies, coolant piping, etc. The CF grades of CASS alloys are the cast equivalents of 300-series stainless steels (SSs) and show excellent mechanical properties and corrosion resistance. In contrast to the fully austenitic microstructure of wrought SSs, CASS alloys consist of a dual-phase microstructure of delta ferrite and austenite and are vulnerable to thermal aging embrittlement. The service performance of CASS alloys is of concern after long-term exposure to high-temperature coolant. In this work, we studied the effects of thermal aging and ferrite content on the fracture resistance of CASS alloys. Crack growth rate and fracture toughness J–R curve tests were performed on aged and unaged CASS alloys in simulated light water reactor environments. The impact of thermal aging on the cracking susceptibility was investigated and the effect of ferrite content was evaluated. Significant embrittlement was observed in the CASS alloys after aging at 400°C. To understand the embrittlement mechanism, microstructural characterizations were performed with transmission electron microscope. The thermal aging produced G-phase precipitates and phase separation in the ferrite, but did not affect the microstructure of austenite. Consequently, the ferrite was hardened considerably after thermal aging while the hardness of austenite phase remained unchanged. The difference in hardness created a high incompatible strain at the interface between ferrite and austenite, leading to fracture at phase boundaries. |
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"In situ high-energy X-ray diffraction study of tensile deformation of neutron-irradiated polycrystalline Fe-9%Cr alloy" Meimei Li, Jun-Sang Park, Peter Kenesei, Jonathan Almer, Chi Xu, James F. Stubbins, Xuan Zhang, [2017] Acta Materialia · DOI: 10.1016/j.actamat.2016.12.038 · EID: 2-s2.0-85007480798 · ISSN: 1359-6454 | |
"iRadMat: A thermo-mechanical testing system for in situ high-energy X-ray characterization of radioactive specimens"
Chi Xu, Leyun Wang, Yiren Chen, Meimei Li, Jonathan D. Almer, Erika Benda, Peter Kenesei, Ali Mashayekhi, Jun-Sang Park, Frank J. Westferro, Xuan Zhang,
[2017]
Review of Scientific Instruments
· DOI: 10.1063/1.4974246
· EID: 2-s2.0-85010712165
· ISSN: 1089-7623
We present an in situ Radiated Materials (iRadMat) experimental module designed to interface with a servo-hydraulic load frame for X-ray measurements at beamline 1-ID at the Advanced Photon Source. This new capability allows in situ studies of radioactive specimens subject to thermo-mechanical loading using a suite of high-energy X-ray scattering and imaging techniques. The iRadMat is a radiation-shielded vacuum heating system with the sample rotation-under-load capability. We describe the design features and performances of the iRadMat and present a dataset from a 300 °C uniaxial tensile test of a neutron-irradiated pure Fe specimen to demonstrate its capabilities. |
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"3D study of neutron irradiation effects on tensile deformation in Fe-based alloys using high energy synchrotron X-rays" [2016] Transactions of the American Nuclear Society · EID: 2-s2.0-85117939544 · ISSN: 0003-018X | |
"Characterization of neutron-irradiated HT-UPS steel by high-energy X-ray diffraction microscopy" Jun-Sang Park, Jonathan Almer, Meimei Li, Xuan Zhang, [2016] Journal of Nuclear Materials · DOI: 10.1016/j.jnucmat.2015.11.063 · EID: 2-s2.0-84960303874 · ISSN: 0022-3115 | |
"In-situ high energy x-ray characterization of tensile deformation of advanced austenitic stainless steels" [2016] Transactions of the American Nuclear Society · EID: 2-s2.0-85117897281 · ISSN: 0003-018X | |
"Irradiation-induced formation of nanorod precipitates in a dilute Cu-W alloy" Xuan Zhang, John A. Beach, Pascal Bellon, Robert S. Averback, Shipeng Shu, [2016] Scripta Materialia · DOI: 10.1016/j.scriptamat.2016.01.012 · EID: 2-s2.0-84960472766 · ISSN: 1359-6462 | |
"Microstructural evolution of NF709 (20Cr-25Ni-1.5MoNbTiN) under neutron irradiation" L. Tan, C. Xu, Y. Yang, X. Zhang, M. Li, B.K. Kim, [2016] Journal of Nuclear Materials · DOI: 10.1016/j.jnucmat.2015.12.037 · EID: 2-s2.0-84952683848 · ISSN: 0022-3115 | |
"Non-equilibrium grain boundary wetting in Cu–Ag alloys containing W nanoparticles" Xuan Zhang, Pascal Bellon, Robert S. Averback, Shipeng Shu, [2016] Materials Research Letters · DOI: 10.1080/21663831.2015.1090496 · EID: 2-s2.0-85009288337 · ISSN: 2166-3831 | |
"Precipitation kinetics of dilute Cu-W alloys during low-temperature ion irradiation" John A. Beach, Miao Wang, Pascal Bellon, Robert S. Averback, Xuan Zhang, [2016] Acta Materialia · DOI: 10.1016/j.actamat.2016.08.043 · EID: 2-s2.0-84983613509 · ISSN: 1359-6454 | |
"High-energy synchrotron x-ray techniques for studying irradiated materials" Xuan Zhang, Hemant Sharma, Peter Kenesei, David Hoelzer, Meimei Li, Jonathan Almer, Jun-Sang Park, [2015] Journal of Materials Research · DOI: 10.1557/jmr.2015.50 · EID: 2-s2.0-84929670368 · ISSN: 2044-5326 | |
"In situ TEM study of G-phase precipitates under heavy ion irradiation in CF8 cast austenitic stainless steel" Meimei Li, Xuan Zhang, Marquis A. Kirk, Peter M. Baldo, Tiangan Lian, Wei-Ying Chen, [2015] Journal of Nuclear Materials · DOI: 10.1016/j.jnucmat.2015.04.042 · EID: 2-s2.0-84929088504 · ISSN: 0022-3115 | |
"Irradiation-Induced Nanoprecipitation in Ni-W Alloys" Calvin R. Lear, Xuan Zhang, Pascal Bellon, Robert S. Averback, Jaeyel Lee, [2015] Metallurgical and Materials Transactions A: Physical Metallurgy and Materials Science · DOI: 10.1007/s11661-014-2704-4 · EID: 2-s2.0-84925465147 · ISSN: 1073-5623 | |
"Precipitate stability in Cu-Ag-W system under high-temperature irradiation" Shipeng Shu, Pascal Bellon, Robert S. Averback, Xuan Zhang, [2015] Acta Materialia · DOI: 10.1016/j.actamat.2015.06.045 · EID: 2-s2.0-84937568537 · ISSN: 1359-6454 | |
"A kinetic Monte Carlo study of coarsening resistance of novel core/shell precipitates" Wenpei Gao, Pascal Bellon, Robert S. Averback, Jian-Min Zuo, Xuan Zhang, [2014] Acta Materialia · DOI: 10.1016/j.actamat.2014.07.010 · EID: 2-s2.0-84905327842 · ISSN: 1359-6454 | |
"Irradiation-induced selective precipitation in Cu-Nb-W alloys: An approach towards coarsening resistance" Jianguo Wen, Pascal Bellon, Robert S. Averback, Xuan Zhang, [2013] Acta Materialia · DOI: 10.1016/j.actamat.2012.12.020 · EID: 2-s2.0-84873993454 · ISSN: 1359-6454 | |
"Microstructural stability of nanostructured Cu-Nb-W alloys during high-temperature annealing and irradiation" N.Q. Vo, P. Bellon, R.S. Averback, X. Zhang, [2011] Acta Materialia · DOI: 10.1016/j.actamat.2011.05.009 · EID: 2-s2.0-79959517817 · ISSN: 1359-6454 | |
"Microstructural stability of nanostructured Cu alloys during high-temperature irradiation" See W. Chee, Daniel Schwen, Xuan Zhang, Pascal Bellon, Robert S. Averback, Nhon Q. Vo, [2010] Scripta Materialia · DOI: 10.1016/j.scriptamat.2010.07.009 · EID: 2-s2.0-77955981600 · ISSN: 1359-6462 | |
Source: ORCID/CrossRef using DOI |
This NSUF Profile is 60
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The Nuclear Science User Facilities (NSUF) is the U.S. Department of Energy Office of Nuclear Energy's only designated nuclear energy user facility. Through peer-reviewed proposal processes, the NSUF provides researchers access to neutron, ion, and gamma irradiations, post-irradiation examination and beamline capabilities at Idaho National Laboratory and a diverse mix of university, national laboratory and industry partner institutions.
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