NSUF - Nuclear Science User Facilities

Lizhen Tan

Profile Information
Name
Dr. Lizhen Tan
Institution
Oak Ridge National Laboratory
Position
Research Staff
Affiliation
Oak Ridge National Laboratory
h-Index
ORCID
0000-0002-3418-2450
Publications:
"Advanced synchrotron characterization techniques for fusion materials science" David Sprouster, J Trelewicz, Lance Snead, Daniel Morrall, Takaaki Koyanagi, X Hu, Chad Parish, Lizhen Tan, Yutai Katoh, Brian Wirth, Journal of Nuclear Materials Vol. 543 2020 152574 Link
"Enhanced diffusion of Cr in 20Cr-25Ni type alloys under proton irradiation at 670 °C" Tianyi Chen, ying yang, Li He, Beata Tyburska-Puschel, Kumar Sridharan, Haixuan Xu, Lizhen Tan, Nuclear Materials and Energy Vol. 17 2018 142-146 Link
"Evolution dependence of vanadium nitride nanoprecipitates on directionality of ion irradiation" Bong Goo Kim, Lizhen Tan, Gary Was, Journal of Nuclear Materials Vol. 495 2017 425-430 Link
The influence of the directionality of Fe2+ ion irradiation on the evolution of vanadium nitride platelet–shaped nanoprecipitates at 500 °C was investigated in a ferritic alloy using transmission electron microscopy. When the ion-irradiation direction was approximately aligned with the initial particle length, particles grew longer and sectioned into shorter lengths at higher doses, resulting in increased particle densities. As ion-irradiation direction deviated from particle-length direction, some particles sectioned lengthwise and then dissolved, resulting in decreased particle densities. Surviving particles were transformed into parallelograms with a different orientation relationship with the matrix. Nanoprecipitate evolution dependence on beam-nanoprecipitate orientation is a process that may be different from reactor irradiation.
"Helium sequestration at nanoparticle-matrix interfaces in helium + heavy ion irradiated nanostructured ferritic alloys" Yutai Katoh, Chad Parish, Lizhen Tan, Steven Zinkle, Kinga Unocic, Sosuke Kondo, Lance Snead, David Hoelzer, Journal of Nuclear Materials Vol. 483 2017 21-34 Link
We irradiated four ferritic alloys with energetic Fe and He ions: one castable nanostructured alloy (CNA) containing Ti-W-Ta-carbides, and three nanostructured ferritic alloys (NFAs). The NFAs were: 9Cr containing Y-Ti-O nanoclusters, and two Fe-12Cr-5Al NFAs containing Y-Zr-O or Y-Hf-O clusters. All four were subjected to simultaneous dual-beam Fe + He ion implantation (650 °C, ~50 dpa, ~15 appm He/dpa), simulating fusion-reactor conditions. Examination using scanning/transmission electron microscopy (STEM) revealed high-number-density helium bubbles of ~8 nm, ~1021 m-3 (CNA), and of ~3 nm, 1023 m-3 (NFAs). STEM combined with multivariate statistical analysis data mining suggests that the precipitate-matrix interfaces in all alloys survived ~50 dpa at 650 °C and serve as effective helium trapping sites. All alloys appear viable structural material candidates for fusion or advanced fission energy systems. Among these developmental alloys the NFAs appear to sequester the helium into smaller bubbles and away from the grain boundaries more effectively than the early-generation CNA.
"High-temperature strengthening mechanisms of Laves and B2 precipitates in a novel ferritic alloy" Tianyi Chen, Chad Parish, Ying Yang, Lizhen Tan, Materials Science and Engineering: A Vol. 720 2018 110-116 Link
Precipitates of the Laves and B2 phases were engineered in a newly-designed advanced ferritic alloy. Under creep test at 650 °C with 120 MPa, the material showed a steady-state minimum creep rate of 1 × 10−4 h−1, about one order of magnitude lower than T91. Microstructural characterization of the ferritic alloy revealed primarily ductile and partially brittle fractures after the creep test. Coarse Laves phase (~ 1 µm) was observed associating with the brittle fracture, resulting in reduced creep ductility. However, fine Laves phase precipitates (~ 100 nm) helped the dimple-ductile fracture and strengthened the material through impeding the motion of dislocations and boundaries. Unlike the B2 precipitates remained coherent exerting the classic Orowan bypassing mechanism at the brittle location, some of the B2 precipitates at the ductile location became incoherent and can develop an attractive interaction with dislocations. This coherency change of B2 precipitates, together with the nucleation of ultrafine (~ 40 nm) Laves phase precipitates during the creep test, would compensate for the coarsening-induced loss of Orowan strengthening of coherent B2 precipitates.
"Integrated Computational Study of Radiation Damage Effects in Grade 92 Steel and Alloy 709" Haixuan Xu, Lizhen Tan, Li He, Vol. 2019 Link
"Measurement of Irradiation-induced Swelling in Stainless Steels with a New Transmission Electron Microscopy Method" Li He, Haixuan Xu, Lizhen Tan, Paul Voyles, Kumar Sridharan, Microscopy and Microanalysis Vol. 23 2017 2234-2235 Link
"Microstructural evolution in Fe-20Cr-25Ni austenitic alloys under proton irradiation at 670 ºC" Tianyi Chen, Lizhen Tan, Li He, Beata Tyburska-Puschel, Kumar Sridharan, Transactions of American Nuclear Society Vol. 117 2017 581-583 Link
"Microstructural evolution of neutron-irradiated T91 and NF616 to ~4.3 dpa at 469 °C" Kevin Field, Bong Goo Kim, Lizhen Tan, Yong Yang, Sean Gray, Meimei Li, Journal of Nuclear Materials Vol. 493 2017 12-20 Link
Ferritic-martensitic steels such as T91 and NF616 are candidate materials for several nuclear applications. This study evaluates radiation resistance of T91 and NF616 by examining their microstructural evolutions and hardening after the samples were irradiated in the Advanced Test Reactor to ∼4.3 displacements per atom (dpa) at an as-run temperature of 469 °C. In general, this irradiation did not result in significant difference in the radiation-induced microstructures between the two steels. Compared to NF616, T91 had a higher number density of dislocation loops and a lower level of radiation-induced segregation, together with a slightly higher radiation-hardening. Unlike dislocation loops developed in both steels, radiation-induced cavities were only observed in T91 but remained small with sub-10 nm sizes. Other than the relatively stable M23C6, a new phase (likely Sigma phase) was observed in T91 and radiation-enhanced MX → Z phase transformation was identified in NF616. Laves phase was not observed in the samples.
"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.
"Microstructure and property tailoring of castable nanostructured alloys through thermomechanical treatments" Lizhen Tan, Chad Parish, Journal of Nuclear Materials Vol. 509 2018 267-275 Link
Three types of microstructures, i.e., tempered-martensite (TM), ferrite (F), and dual-phase (TM + F), were developed in a castable nanostructured alloy that favors a high density of nanoprecipitates compared with the precipitates in current reduced-activation ferritic-martensitic steels. The effect of the distinct microstructures on tensile properties, Charpy impact toughness, and thermal helium desorption behavior was investigated with the full TM structure as a reference. The results indicated that the F domain in the TM + F structure governed the strength and slightly impaired the impact toughness. The full F structure exhibited the highest strength without compromising ductility, but it noticeably diminished impact toughness. All microstructures had a dominant helium desorption peak at ∼1070 °C. The higher density of nanoprecipitates and complex boundaries and dislocations in the TM + F structure enhanced the secondary helium desorption peak and extended the shoulder peak, in contrast to the full TM structure with an enlarged desorption peak associated with the ferrite-to-austenite transformation at ∼810–850 °C and the full F structure with a dominant desorption peak related to bubble migration at ∼1070 °C. These results suggest that components fabricated from functionally graded microstructures could be engineered to exploit the advantages of different microstructures for demanding application requirements.
"Neutron irradiation induced defects and clustering in NF616 and T91" Weicheng Zhong, Tarik Saleh, Lizhen Tan, Journal of Nuclear Materials Vol. 552 2021 Link
"Phase Stability in the Fe-Rich Fe-Cr-Ni-Zr Alloys" Tianyi Chen, Lizhen Tan, ying yang, Metallurgical and Materials Transactions A Vol. 48 2017 5009-5016 Link
Knowledge on phase stability in Fe-rich Fe-Cr-Ni-Zr alloys is needed for the development of Laves phase strengthened Fe-Cr-Ni-Zr ferritic alloys. These alloys show promising applications as new cladding materials of nuclear reactors due to enhanced high-temperature strength and resistance to creep and irradiation hardening. Phase stability in four Fe-rich Fe-Cr-Ni-Zr alloys was carefully investigated using scanning electron microscopy, transmission electron microscopy, energy-dispersive X-ray spectroscopy, and X-ray diffraction techniques. The samples were arc-melted and heat treated at 973.15 K (700 °C) for 1275 hours and 1273.15 K (1000 °C) for 336 hours. The experimental results showed extensive solubility of Ni in the intermetallic phases Fe23Zr6 and Fe2Zr_C15. Nickel stabilizes the Laves Fe2Zr_C15 structure more than the C36 and C14 structures. In addition to Fe23Zr6 and Fe2Zr_C15, Ni7Zr2 was found to be stable in samples with higher Ni content and lower annealing temperature. The Fe2Zr_C15 and Fe23Zr6 coexist with the body-centered cubic matrix phase in all samples regardless of compositions and temperatures.
"Stability of MX-type strengthening nanoprecipitates in ferritic steels under thermal aging, stress and ion irradiation" Yutai Katoh, Lizhen Tan, Lance Snead, Thak Sang Byun, Acta Materialia Vol. 71 2014 11–19 Link
The stability of MX-type precipitates is critical to retain mechanical properties of both reduced activation ferritic–martensitic (RAFM) and conventional FM steels at elevated temperatures above 500 C. The stability of TaC, TaN and VN nanoprecipitates under thermal aging (600 and 700 C), creep (600 C) and ion irradiation (Fe ion, 500 C) conditions was systematically studied in this work. The statistical particle evolution in density and size was characterized using transmission electron microscopy. Nanoprecipitate stability under the studied conditions manifested differently through either dissolution, reprecipitation, growth or fragmentation, with TaC exhibiting the greatest stability followed by VN and TaN in sequence. Nanoprecipitate evolution phenomena and mechanisms and the apparent disagreement of this interpretation with published literature on the subject are discussed. These findings not only help understanding the degradation mechanisms of RAFM and conventional FM steels at elevated temperatures and under stress and irradiation, but should also prove beneficial to the development of advanced RAFM steels.
"Stability of the Strengthening Nanoprecipitates in Reduced Activation Ferritic Steels Under Fe2+ Ion Irradiation" Yutai Katoh, Lance Snead, Lizhen Tan, Journal of Nuclear Materials Vol. 445 2014 104-110 Link
The stability of MX-type precipitates is critical to retain mechanical properties of both reduced activation ferritic–martensitic (RAFM) and conventional FM steels at elevated temperatures. Radiation resistance of TaC, TaN, and VN nanoprecipitates irradiated up to ~49 dpa at 500 °C using Fe2+ is investigated in this work. Transmission electron microscopy (TEM) utilized in standard and scanning mode (STEM) reveals the non-stoichiometric nature of the nanoprecipitates. Irradiation did not alter their crystalline nature. The radiation resistance of these precipitates, in an order of reduced resistance, is TaC, VN, and TaN. Particle dissolution, growth, and reprecipitation were the modes of irradiation-induced instability. Irradiation also facilitated formation of Fe2W type Laves phase limited to the VN and TaN bearing alloys. This result suggests that nitrogen level should be controlled to a minimal level in alloys to gain greater radiation resistance of the MX-type precipitates at similar temperatures as well as postpone the formation and subsequent coarsening of Laves phase.
Presentations:
"Ion Irradiation Defects in Austenitic Alloy 709 and Ferritic-Martensitic Steel Grade 92 for Nuclear Applications" Li He, Rigen Mo, Beata Tyburska-Puschel, Kumar Sridharan, Haixuan Xu, Tianyi Chen, Lizhen Tan, MRS Spring 2017 April 17-21, (2017)
"Radiation response of Grade 92 ferritic-martensitic steel irradiated up to 14.63 dpa at ~700°C" Weicheng Zhong, Lizhen Tan, TMS 2020 Annual Meeting & Exhibition February 23-27, (2020) Link
"Stability of MX Nanoprecipitates in Ferritic Steels Under Thermal, Stress, and Ion Irradiation" Yutai Katoh, Lance Snead, Lizhen Tan, Gary Was, 16th International Conference on Fusion Reactor Materials (ICFRM-16) October 20-26, (2013)
"Study of B2 and Laves Phase E volution in a Novel Ferr itic Steel under Ion Irradiation" Li He, Lizhen Tan, ying yang, Kumar Sridharan, MiNES (Materials in Nuclear Energy Systems) 2019 October 6-10, (2019)
NSUF Articles:
U.S. Department of Energy Announces FY17 CINR FOA Awards - DOE selected 14 NSUF projects DOE selected five university, four national laboratory, and five industry-led projects that will take advantage of NSUF capabilities to investigate important nuclear fuel and material applications. Wednesday, September 20, 2017 - Calls and Awards
NSUF Researcher Feature: Kumar Sridharan - Learn more about a University of Wisconsin professor who helped kick start NSUF Sridharan's research team put the NSUF's first material samples into the ATR, launching a new era of research into the behaviors of fuels and materials in a nuclear reactor environment. Wednesday, August 28, 2019 - Newsletter, Researcher Highlight
DOE Awards 37 RTE Proposals - Awarded projects total nearly $1.4M in access awards Tuesday, July 14, 2020 - News Release, Calls and Awards
Additional Publications:
"Creep behavior of an additively manufactured 9Cr steel in the as-built condition" Weicheng Zhong, Ying Yang, Kevin G. Field, Niyanth Sridharan, Andrew T. Nelson, Lizhen Tan, [2022] Journal of Nuclear Materials · DOI: 10.1016/j.jnucmat.2022.153943
"Long-Term Thermal Aging Effect Evaluation for Grade 92 and 316L at The LWR Relevant Temperature" Xiang Chen, Lizhen Tan, [2021] · DOI: 10.2172/1843699
"Microstructure and mechanical properties of high Mn-containing ferritic-martensitic alloys exposed to cyclical thermal treatment" Ying Yang, Kevin G. Field, Niyanth Sridharan, Kurt Terrani, Lizhen Tan, Weicheng Zhong, [2021] Materials Science and Engineering: A · DOI: 10.1016/j.msea.2021.141143
"Segregation behavior and phase instability of Eurofer97 after neutron irradiation to 72 dpa" Chad M. Parish, Kevin G. Field, Lizhen Tan, Yutai Katoh, Kun Wang, [2021] Journal of Nuclear Materials · DOI: 10.1016/j.jnucmat.2021.152834
"Effects of helium on irradiation response of reduced-activation ferritic-martensitic steels: Using nickel isotopes to simulate fusion neutron response" L. Tan, H. Sakasegawa, C.M. Parish, W. Zhong, H. Tanigawa, Y. Katoh, B.K. Kim, [2021] Journal of Nuclear Materials · DOI: 10.1016/j.jnucmat.2020.152634
"Microstructures and mechanical properties of a modified 9Cr ferritic-martensitic steel in the as-built condition after additive manufacturing" Niyanth Sridharan, Dieter Isheim, Kevin G. Field, Ying Yang, Kurt Terrani, Lizhen Tan, Weicheng Zhong, [2021] Journal of Nuclear Materials · DOI: 10.1016/j.jnucmat.2020.152742
"Advanced synchrotron characterization techniques for fusion materials science" J.R. Trelewicz, L.L. Snead, X. Hu, D. Morrall, T. Koyanagi, C.M. Parish, L. Tan, Y. Katoh, B.D. Wirth, D.J. Sprouster, [2021] Journal of Nuclear Materials · DOI: 10.1016/j.jnucmat.2020.152574
"ORNL Post-irradiation Examination (LAMDA) Final Report on Characterization of Irradiated Grade 92 Ferritic-Martensitic Steels" Lizhen Tan, Kory Linton, Weicheng Zhong, [2020] · DOI: 10.2172/1765483
"Intermediate-Term Thermal Aging Effect Evaluation for Grade 92 and 316L at The LWR Relevant Temperature" Xiang (Frank) Chen, Lizhen Tan, [2020] · DOI: 10.2172/1761620
"The correlation between microstructure and nanoindentation property of neutron-irradiated austenitic alloy D9" Lingfeng He, Mack H. Cullison, Charles Hay, Jatuporn Burns, Yaqiao Wu, Lizhen Tan, Tianyi Chen, [2020] Acta Materialia · DOI: 10.1016/j.actamat.2020.05.020
"Microstructural stability of tantalum-alloyed ferritic-martensitic steel with neutron irradiation to 7.4 dpa at ~490 °C" W. Zhong, T. Chen, L. Tan, [2020] Materialia · DOI: 10.1016/j.mtla.2020.100608
"Report on partially complete post-irradiation-examination of the INL samples" Lizhen Tan, Weicheng Zhong, [2020] · DOI: 10.2172/1651352
"Second Annual Progress Report on Correlation Between Microstructure and Mechanical Properties of Neutron-Irradiated Ferritic-Martensitic and Austenitic Steels" Lizhen Tan, Weicheng Zhong, [2020] · DOI: 10.2172/1651349
"Contrasting roles of Laves_Cr2Nb precipitates on the creep properties of novel CuCrNbZr alloys" Ce Zheng, Boopathy Kombaiah, Lizhen Tan, David J. Sprouster, Lance L. Snead, Steven J. Zinkle, Ying Yang, Ling Wang, [2020] Materials Science and Engineering A · DOI: 10.1016/j.msea.2020.139110 · EID: 2-s2.0-85080908509
"Coupling computational thermodynamics with density-function-theory based calculations to design L12 precipitates in Fe[sbnd]Ni based alloys" German D. Samolyuk, Tianyi Chen, Jonathan D. Poplawsky, Andrew R. Lupini, Lizhen Tan, Littrell Ken, Ying Yang, [2020] Materials and Design · DOI: 10.1016/j.matdes.2020.108592 · EID: 2-s2.0-85081032175
"Post-Irradiation-Examination of the ORNL and LANL Samples" Lizhen Tan, Kory Linton, Tarik Saleh, Weicheng Zhong, [2019] · DOI: 10.2172/1651367
"NSUF Tensile Testing and Characterization of Irradiated Grade 92 Ferritic-Martensitic Steels" Weicheng Zhong, Lizhen Tan, Kory Linton, Ben Garrison, [2019] · DOI: 10.2172/1524855
"Deuterium retention in advanced steels for fusion reactor structural application" Lizhen Tan, Kun Wang, Caleb P. Massey, David T. Hoelzer, Yutai Katoh, Xunxiang Hu, [2019] Journal of Nuclear Materials · DOI: 10.1016/j.jnucmat.2019.01.020
"Interactions between displacement cascade and dislocation and their influences on Peierls stress in Fe-20Cr-25Ni alloys" Liubin Xu, Tianyi Chen, Lizhen Tan, Haixuan Xu, Zizhe Lu, [2019] Computational Materials Science · DOI: 10.1016/j.commatsci.2018.12.018
"Development of nanoprecipitates-strengthened advanced ferritic alloys for nuclear reactor applications" Tianyi Chen, Ying Yang, Li He, Kumar Sridharan, Lizhen Tan, [2019] · DOI: 10.2172/1526385
"First Annual Progress Report on the Procurement and Post-Irradiation Examination of the Selected Samples of Alloy 800H and Grade 92 and 91 Steels" Tianyi Chen, Kory Linton, Collin Knight, Tarik Saleh, Lizhen Tan, [2019] · DOI: 10.2172/1526384
"Identification and Shipment Progress of the INL and LANL Samples to Be Received at ORNL" Kory Linton, Collin Knight, Tarik Saleh, Lizhen Tan, [2019] · DOI: 10.2172/1506784
"Partial completion of post-irradiation examination of the ORNL samples" Tianyi Chen, Lizhen Tan, [2019] · DOI: 10.2172/1507852
"Report on The Down-Selected Nanoprecipitates-Strengthened Advanced Ferritic Alloys for Nuclear Reactor Applications" Tianyi Chen, Ying Yang, Li He, Kumar Sridharan, Lizhen Tan, [2019] · DOI: 10.2172/1506786
"Evolution of B2 and laves phases in a ferritic steel under Fe2+ ion irradiation at 475 °C" Lizhen Tan, Ying Yang, Kumar Sridharan, Li He, [2019] Journal of Nuclear Materials · DOI: 10.1016/j.jnucmat.2019.07.024 · EID: 2-s2.0-85069947060
"Research tools: Microstructure, mechanical properties, and computational thermodynamics" Jonathan M. Hyde, G. Robert Odette, Gene E. Lucas, Lizhen Tan, Colin A. English, [2019] Structural Alloys for Nuclear Energy Applications · DOI: 10.1016/b978-0-12-397046-6.00004-6 · EID: 2-s2.0-85081311356
"Steam oxidation behavior of Ni-base superalloys 690, 725 and X-750 at 600 and 650 °C" T. Chen, B.A. Pint, L. Tan, [2019] Corrosion Science · DOI: 10.1016/j.corsci.2019.06.014 · EID: 2-s2.0-85068082339
"Integrated Computational Study of Radiation Damage Effects in Grade 92 Steel and Alloy 709" Lizhen Tan, Li He, Kumar Sridharan, Haixuan Xu, [2018] · DOI: 10.2172/1528716
"Development of castable nanostructured alloys as a new generation RAFM steels" Y. Katoh, L.L. Snead, L. Tan, [2018] Journal of Nuclear Materials · DOI: 10.1016/j.jnucmat.2018.05.024
"Enhanced diffusion of Cr in 20Cr-25Ni type alloys under proton irradiation at 670 °C" Ying Yang, Li He, Beata Tyburska-Püschel, Kumar Sridharan, Haixuan Xu, Lizhen Tan, Tianyi Chen, [2018] Nuclear Materials and Energy · DOI: 10.1016/j.nme.2018.10.001
"Enhanced diffusion of Cr in 20Cr-25Ni type alloys under proton irradiation at 670 °C" Ying Yang, Li He, Beata Tyburska-Püschel, Kumar Sridharan, Haixuan Xu, Lizhen Tan, Tianyi Chen, [2018] Nuclear Materials and Energy · DOI: 10.1016/j.nme.2018.10.001 · EID: 2-s2.0-85055174762
"Metallurgical aspects influencing the resistance to steam oxidation and fracture toughness of select advanced replacement alloys for LWR core internals" Tianyi Chen, Bruce Pint, Lizhen Tan, [2018] · DOI: 10.2172/1490721
"Microstructure and property tailoring of castable nanostructured alloys through thermomechanical treatments" C.M. Parish, X. Hu, L. Tan, [2018] Journal of Nuclear Materials · DOI: 10.1016/j.jnucmat.2018.07.012
"Assessment of the propensity of low creep ductility for optimized Grade 92 steel" Lizhen Tan, [2018] · DOI: 10.2172/1484118
"Materials-engineering challenges for the fusion core and lifetime components of the fusion nuclear science facility" C.E. Kessel, Y. Katoh, L.M. Garrison, L. Tan, Y. Yamamoto, F.W. Wiffen, A.F. Rowcliffe, [2018] Nuclear Materials and Energy · DOI: 10.1016/j.nme.2018.05.025
"Tensile Testing of Irradiated Grade 92 Ferritic-Martensitic Steels at the IMET Hot Cell Facility" Lizhen Tan, Hideo Sakasegawa, Kory Linton, Alicia Raftery, [2018] · DOI: 10.2172/1435195
"High-temperature strengthening mechanisms of Laves and B2 precipitates in a novel ferritic alloy" Chad M. Parish, Ying Yang, Lizhen Tan, Tianyi Chen, [2018] Materials Science and Engineering A · DOI: 10.1016/j.msea.2018.02.013 · EID: 2-s2.0-85042305736
"Materials challenges for the fusion nuclear science facility" L.M. Garrison, Y. Yamamoto, L. Tan, Y. Katoh, A.F. Rowcliffe, [2018] Fusion Engineering and Design · DOI: 10.1016/j.fusengdes.2017.07.012 · EID: 2-s2.0-85025127085
"Mechanical properties and radiation resistance of nanoprecipitates-strengthened advanced ferritic alloys" Ying Yang, Tianyi Chen, Kumar Sridharam, Li He, Lizhen Tan, [2017] · DOI: 10.2172/1427634
"Evolution dependence of vanadium nitride nanoprecipitates on directionality of ion irradiation" B.K. Kim, G.S. Was, L. Tan, [2017] Journal of Nuclear Materials · DOI: 10.1016/j.jnucmat.2017.09.001
"Microstructural evolution of neutron-irradiated T91 and NF616 to ∼4.3 dpa at 469 °C" B.K. Kim, Y. Yang, K.G. Field, S. Gray, M. Li, L. Tan, [2017] Journal of Nuclear Materials · DOI: 10.1016/j.jnucmat.2017.05.041
"Fracture toughness evaluation of select advanced replacement alloys for LWR core internals" Xiang Chen, Lizhen Tan, [2017] · DOI: 10.2172/1394376
"Development of next generation tempered and ODS reduced activation ferritic/martensitic steels for fusion energy applications" J.L. Boutard, D.T. Hoelzer, A. Kimura, R. Lindau, G.R. Odette, M. Rieth, L. Tan, H. Tanigawa, S.J. Zinkle, [2017] Nuclear Fusion · DOI: 10.1088/1741-4326/57/9/092005 · EID: 2-s2.0-85028005248
"Helium sequestration at nanoparticle-matrix interfaces in helium + heavy ion irradiated nanostructured ferritic alloys" K.A. Unocic, L. Tan, S.J. Zinkle, S. Kondo, L.L. Snead, D.T. Hoelzer, Y. Katoh, C.M. Parish, [2017] Journal of Nuclear Materials · DOI: 10.1016/j.jnucmat.2016.10.038 · EID: 2-s2.0-84993965341
"Microstructural evolution in Fe-20Cr-25Ni austenitic alloys under proton irradiation at 670 ºC" [2017] Transactions of the American Nuclear Society · EID: 2-s2.0-85055204441
"Phase Stability in the Fe-Rich Fe-Cr-Ni-Zr Alloys" Ying Yang, Lizhen Tan, Tianyi Chen, [2017] Metallurgical and Materials Transactions A: Physical Metallurgy and Materials Science · DOI: 10.1007/s11661-017-4253-0 · EID: 2-s2.0-85026526005
"The effect of grain orientation on nanoindentation behavior of model austenitic alloy Fe-20Cr-25Ni" Lizhen Tan, Zizhe Lu, Haixuan Xu, Tianyi Chen, [2017] Acta Materialia · DOI: 10.1016/j.actamat.2017.07.028 · EID: 2-s2.0-85025663070
"Recent status and improvement of reduced-activation ferritic-martensitic steels for high-temperature service" Y. Katoh, A.-A.F. Tavassoli, J. Henry, M. Rieth, H. Sakasegawa, H. Tanigawa, Q. Huang, L. Tan, [2016] Journal of Nuclear Materials · DOI: 10.1016/j.jnucmat.2016.07.054
"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
"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
"Development of new generation reduced activation ferritic-martensitic steels for advanced fusion reactors" L.L. Snead, Y. Katoh, L. Tan, [2016] Journal of Nuclear Materials · DOI: 10.1016/j.jnucmat.2016.05.037 · EID: 2-s2.0-84971440563
"Microstructural Evolution of Type 304 and 316 Stainless Steels Under Neutron Irradiation at LWR Relevant Conditions" R. E. Stoller, K. G. Field, Y. Yang, H. Nam, D. Morgan, B. D. Wirth, M. N. Gussev, J. T. Busby, L. Tan, [2016] Jom · DOI: 10.1007/s11837-015-1753-5
"Formulating the strength factor α for improved predictability of radiation hardening" J.T. Busby, L. Tan, [2015] Journal of Nuclear Materials · DOI: 10.1016/j.jnucmat.2015.07.009 · EID: 2-s2.0-84937158926
"In situ phase transformation of Laves phase from Chi-phase in Mo-containing Fe-Cr-Ni alloys" Y. Yang, L. Tan, [2015] Materials Letters · DOI: 10.1016/j.matlet.2015.06.018 · EID: 2-s2.0-84935833473
"Microstructure and Mechanical Properties of Laves Phase-strengthened Fe-Cr-Zr Alloys" Y. Yang, L. Tan, [2015] Metallurgical and Materials Transactions A: Physical Metallurgy and Materials Science · DOI: 10.1007/s11661-014-2695-1 · EID: 2-s2.0-84925534023
"Thermal Stability of Intermetallic Phases in Fe-rich Fe-Cr-Ni-Mo Alloys" Lizhen Tan, Jeremy T. Busby, Ying Yang, [2015] Metallurgical and Materials Transactions A: Physical Metallurgy and Materials Science · DOI: 10.1007/s11661-015-2997-y · EID: 2-s2.0-84938556891
"Effect of Thermal Aging on Coarsening Kinetics of γ′ in Alloy 617" Y. Yang, R. K. Nanstad, J. T. Busby, L. Tan, [2014] Journal of Phase Equilibria and Diffusion · DOI: 10.1007/s11669-014-0312-z · EID: 2-s2.0-84910114602
"Magnetic phase formation in irradiated austenitic alloys" J.T. Busby, L. Tan, F.A. Garner, M.N. Gussev, [2014] Journal of Nuclear Materials · DOI: 10.1016/j.jnucmat.2014.02.005 · EID: 2-s2.0-84897791998
"Stability of MX-type strengthening nanoprecipitates in ferritic steels under thermal aging, stress and ion irradiation" T.S. Byun, Y. Katoh, L.L. Snead, L. Tan, [2014] Acta Materialia · DOI: 10.1016/j.actamat.2014.03.015 · EID: 2-s2.0-84897386993
"Stability of the strengthening nanoprecipitates in reduced activation ferritic steels under Fe2+ ion irradiation" Y. Katoh, L.L. Snead, L. Tan, [2014] Journal of Nuclear Materials · DOI: 10.1016/j.jnucmat.2013.11.003 · EID: 2-s2.0-84888579700
"Strengthening of irradiation-induced defects in AISI304 and 316 variants" [2014] Transactions of the American Nuclear Society · EID: 2-s2.0-84904602276
"Alloying effect of Ni and Cr on irradiated microstructural evolution of type 304 stainless steels" J.T. Busby, L. Tan, [2013] Journal of Nuclear Materials · DOI: 10.1016/j.jnucmat.2013.07.054 · EID: 2-s2.0-84883139130
"Effect of thermomechanical treatment on 9Cr ferritic-martensitic steels" J.T. Busby, P.J. Maziasz, Y. Yamamoto, L. Tan, [2013] Journal of Nuclear Materials · DOI: 10.1016/j.jnucmat.2013.01.323 · EID: 2-s2.0-84885181492
"Effects of alloying elements and thermomechanical treatment on 9Cr Reduced Activation Ferritic-Martensitic (RAFM) steels" Y. Yang, J.T. Busby, L. Tan, [2013] Journal of Nuclear Materials · DOI: 10.1016/j.jnucmat.2012.10.015 · EID: 2-s2.0-84884904648
"Grain boundary engineering for structure materials of nuclear reactors" T.R. Allen, J.T. Busby, L. Tan, [2013] Journal of Nuclear Materials · DOI: 10.1016/j.jnucmat.2013.03.050 · EID: 2-s2.0-84885172367
"Recent progress of R&D activities on reduced activation ferritic/martensitic steels" N. Baluc, Y. Dai, S. Jitsukawa, A. Kimura, J. Konys, R.J. Kurtz, R. Lindau, T. Muroga, G.R. Odette, B. Raj, R.E. Stoller, L. Tan, H. Tanigawa, A.-A.F. Tavassoli, T. Yamamoto, F. Wan, Y. Wu, Q. Huang, [2013] Journal of Nuclear Materials · DOI: 10.1016/j.jnucmat.2012.12.039 · EID: 2-s2.0-84884904393
"Thermodynamic modeling and experimental study of the Fe-Cr-Zr system" Lizhen Tan, Hongbin Bei, Jeremy T. Busby, Ying Yang, [2013] Journal of Nuclear Materials · DOI: 10.1016/j.jnucmat.2013.05.061 · EID: 2-s2.0-84879645136
"Thermomechanical treatment for improved neutron irradiation resistance of austenitic alloy (Fe-21Cr-32Ni)" J.T. Busby, H.J.M. Chichester, K. Sridharan, T.R. Allen, L. Tan, [2013] Journal of Nuclear Materials · DOI: 10.1016/j.jnucmat.2013.01.333 · EID: 2-s2.0-84874770935
"Formation of a magnetic phase in irradiated model austenitic alloys" [2012] Transactions of the American Nuclear Society · EID: 2-s2.0-84876385536
"Material performance in supercritical water" Y. Chen, X. Ren, K. Sridharan, L. Tan, G.S. Was, E. West, D. Guzonas, T.R. Allen, [2012] Comprehensive Nuclear Materials · DOI: 10.1016/b978-0-08-056033-5.00100-2 · EID: 2-s2.0-84867233955
"Microstructural effect on neutron irradiation response of alloy 800H" [2012] Transactions of the American Nuclear Society · EID: 2-s2.0-84876403933
"Microstructure control for high strength 9Cr ferritic-martensitic steels" D.T. Hoelzer, J.T. Busby, M.A. Sokolov, R.L. Klueh, L. Tan, [2012] Journal of Nuclear Materials · DOI: 10.1016/j.jnucmat.2011.12.011 · EID: 2-s2.0-84855769170
"Computational thermodynamics for interpreting oxidation of structural materials in supercritical water" [2011] 15th International Conference on Environmental Degradation of Materials in Nuclear Power Systems-Water Reactors 2011 · EID: 2-s2.0-84867624667
"Corrosion behavior of alloy 800H (Fe-21Cr-32Ni) in supercritical water" T.R. Allen, Y. Yang, L. Tan, [2011] Corrosion Science · DOI: 10.1016/j.corsci.2010.10.021 · EID: 2-s2.0-78650231400
"Corrosion of Austenitic Stainless Steels and Nickel-Base Alloys in Supercritical Water and Novel Control Methods" Todd R. Allen, Ying Yang, Lizhen Tan, [2011] Green Corrosion Chemistry and Engineering: Opportunities and Challenges · DOI: 10.1002/9783527641789.ch8 · EID: 2-s2.0-84884003991
"Corrosion of austenitic and ferritic-martensitic steels exposed to supercritical carbon dioxide" M. Anderson, D. Taylor, T.R. Allen, L. Tan, [2011] Corrosion Science · DOI: 10.1016/j.corsci.2011.06.002 · EID: 2-s2.0-79960702966
"Microstructure optimization of austenitic Alloy 800H (Fe-21Cr-32Ni)" L. Rakotojaona, T.R. Allen, R.K. Nanstad, J.T. Busby, L. Tan, [2011] Materials Science and Engineering A · DOI: 10.1016/j.msea.2010.12.052 · EID: 2-s2.0-79151472644
"Corrosion behavior of 9-12% Cr ferritic-martensitic steels in supercritical water" X. Ren, T.R. Allen, L. Tan, [2010] Corrosion Science · DOI: 10.1016/j.corsci.2009.12.032 · EID: 2-s2.0-77249158792
"Effect of thermomechanical treatment on 9% Cr ferritic-martensitic steels" [2010] Transactions of the American Nuclear Society · EID: 2-s2.0-79551654546
"Effect of thermomechanical treatment on the corrosion of AA5083" T.R. Allen, L. Tan, [2010] Corrosion Science · DOI: 10.1016/j.corsci.2009.10.013 · EID: 2-s2.0-72649088495
"Grain boundary engineering for structure materials of nuclear reactor" [2010] Transactions of the American Nuclear Society · EID: 2-s2.0-79551660143
"High temperature interfacial reactions of TiC, ZrC, TiN, and ZrN with palladium" T.R. Allen, P. Demkowicz, L. Tan, [2010] Solid State Ionics · DOI: 10.1016/j.ssi.2010.06.054 · EID: 2-s2.0-77955557430
"Effect of microstructure on the corrosion of CVD-SiC exposed to supercritical water" T.R. Allen, E. Barringer, L. Tan, [2009] Journal of Nuclear Materials · DOI: 10.1016/j.jnucmat.2009.08.008 · EID: 2-s2.0-70349412915
"Experimental and simulation insight on the transport of silver fission product in SiC" [2009] 2008 Proceedings of the 4th International Topical Meeting on High Temperature Reactor Technology, HTR 2008 · EID: 2-s2.0-70349913611
"Experimental studies on the transport of silver and cesium fission products in SIC" [2009] International Congress on Advances in Nuclear Power Plants 2009, ICAPP 2009 · EID: 2-s2.0-84907941142
"High temperature irradiation effects in selected Generation IV structural alloys" D.A. McClintock, D.T. Hoelzer, L. Tan, T.R. Allen, R.K. Nanstad, [2009] Journal of Nuclear Materials · DOI: 10.1016/j.jnucmat.2009.03.022 · EID: 2-s2.0-67349171048
"Influence of alloy microstructure on oxide growth in HCM12A in supercritical water" [2009] Materials Research Society Symposium Proceedings · EID: 2-s2.0-70449449552
"Localized corrosion of magnetite on ferritic-martensitic steels exposed to supercritical water" T.R. Allen, L. Tan, [2009] Corrosion Science · DOI: 10.1016/j.corsci.2009.08.021 · EID: 2-s2.0-70349416415
"Oxidation performance in supercritical water" [2009] 14th International Conference on Environmental Degradation of Materials in Nuclear Power Systems Water Reactors 2009 · EID: 2-s2.0-78649345860
"Perspectives on corrosion in supercritical water environment: Materials and novel treatments" [2009] NACE - International Corrosion Conference Series · EID: 2-s2.0-69249128658
"Pilot project for irradiation testing of materials at the ATR-national scientific user facility" [2009] Transactions of the American Nuclear Society · EID: 2-s2.0-72749096559
"Altering corrosion response via grain boundary engineering" [2008] Materials Science Forum · EID: 2-s2.0-58149133506
"Corrosion behavior of Ni-base alloys for advanced high temperature water-cooled nuclear plants" X. Ren, K. Sridharan, T.R. Allen, L. Tan, [2008] Corrosion Science · DOI: 10.1016/j.corsci.2008.08.024 · EID: 2-s2.0-54049151521
"EBSD for microstructure and property characterization of the SiC-coating in TRISO fuel particles" T.R. Allen, J.D. Hunn, J.H. Miller, L. Tan, [2008] Journal of Nuclear Materials · DOI: 10.1016/j.jnucmat.2007.04.048 · EID: 2-s2.0-37249000537
"Effect of shot-peening on the oxidation of alloy 800H exposed to supercritical water and cyclic oxidation" X. Ren, K. Sridharan, T.R. Allen, L. Tan, [2008] Corrosion Science · DOI: 10.1016/j.corsci.2008.04.008 · EID: 2-s2.0-47049087520
"High temperature corrosion of materials in supercritical water and liquid lead-alloy environments" Yun Chen, Lizhen Tan, McLean Terrence Machut, Alan Kruizenga, Xiaowei Ren, Todd R. Allen, Kumar Sridharan, [2008] ECS Transactions · DOI: 10.1149/1.2939078 · EID: 2-s2.0-57649149581

The Supercritical Water-cooled Reactor (SCWR) and Lead-cooled Fast Reactor (LFR) are among the six reactor concepts identified by the Generation IV initiative for the next generation nuclear reactors. Materials degradation due to corrosion is a significant issue in both supercritical water and molten lead (-alloy) environments, particularly at the intended higher temperatures of application. In supercritical water, corrosion of ferritic and austenitic steels and Inconel alloys occurs mainly by the growth of an oxide layer on the surface. In molten lead (-alloy), corrosion can occur by dissolution of the material, oxidation, or by the penetration of liquid metal into the material primarily along the grain boundaries. Surface treatment of ferritic steels by the incorporation of thin film of oxidation-resistant materials has been shown to mitigate corrosion in these aggressive environments. Grain boundary engineering (GBE) reduces spallation of oxide layers in austenitic steels in supercritical water environment.
"High temperature irradiation experiments of Gen IV structural metallic materials" [2008] Transactions of the American Nuclear Society · EID: 2-s2.0-55249104821
"Materials challenges for generation IV nuclear energy systems" [2008] Nuclear Technology · EID: 2-s2.0-46849103434
"Microstructure tailoring for property improvements by grain boundary engineering" K. Sridharan, T.R. Allen, R.K. Nanstad, D.A. McClintock, L. Tan, [2008] Journal of Nuclear Materials · DOI: 10.1016/j.jnucmat.2007.08.015 · EID: 2-s2.0-38749154625
"Corrosion and stress corrosion cracking in supercritical water" P. Ampornrat, G. Gupta, S. Teysseyre, E.A. West, T.R. Allen, K. Sridharan, L. Tan, Y. Chen, X. Ren, C. Pister, G.S. Was, [2007] Journal of Nuclear Materials · DOI: 10.1016/j.jnucmat.2007.05.017 · EID: 2-s2.0-34547841442
"Corrosion behavior of a ferritic/martensitic steel HCM12A exposed to harsh environments" M.T. Machut, K. Sridharan, T.R. Allen, L. Tan, [2007] Journal of Nuclear Materials · DOI: 10.1016/j.jnucmat.2007.05.001 · EID: 2-s2.0-34547837515
"Effect of thermomechanical processing on grain boundary character distribution of a Ni-based superalloy" K. Sridharan, T.R. Allen, L. Tan, [2007] Journal of Nuclear Materials · DOI: 10.1016/j.jnucmat.2007.05.002 · EID: 2-s2.0-34547849556
"Thermal and radiation-induced segregation in model Ni-base alloys" L. Tan, G.S. Was, E.A. Kenik, T.R. Allen, [2007] Journal of Nuclear Materials · DOI: 10.1016/j.jnucmat.2006.12.004 · EID: 2-s2.0-33947580178
"Grain boundary engineering of FCC and BCC alloys" [2006] Transactions of the American Nuclear Society · EID: 2-s2.0-33746077777
"Microstructural development in advanced ferritic-martensitic steel HCM12A" L. Tan, J. Gan, G. Gupta, G.S. Was, E.A. Kenik, S. Shutthanandan, S. Thevuthasan, T.R. Allen, [2006] Journal of Nuclear Materials · DOI: 10.1016/j.jnucmat.2006.02.014 · EID: 2-s2.0-33746781354
"Oxidation behavior of HCM12A exposed in Harsh environments" [2006] Transactions of the American Nuclear Society · EID: 2-s2.0-33746102247
"Oxidation behavior of iron-based alloy HCM12A exposed in supercritical water" Y. Yang, T.R. Allen, L. Tan, [2006] Corrosion Science · DOI: 10.1016/j.corsci.2005.10.010 · EID: 2-s2.0-33748793642
"Porosity prediction in supercritical water exposed ferritic/martensitic steel HCM12A" Ying Yang, Todd R. Allen, Lizhen Tan, [2006] Corrosion Science · DOI: 10.1016/j.corsci.2006.05.026 · EID: 2-s2.0-33750628723
"Radiation resistance of advanced ferritic-martensitic steel HCM12A" [2006] ASTM Special Technical Publication · EID: 2-s2.0-40849089764
"The effect of grain boundary engineering on the oxidation behavior of INCOLOY alloy 800H in supercritical water" K. Sridharan, T.R. Allen, L. Tan, [2006] Journal of Nuclear Materials · DOI: 10.1016/j.jnucmat.2005.09.023 · EID: 2-s2.0-29344433453
"An EBSD study of oxidation behavior of an iron-based alloy in supercritical water" [2005] TMS Annual Meeting · EID: 2-s2.0-23244460226
"An electron backscattered diffraction study of grain boundary-engineered INCOLOY Alloy 800H" [2005] Metallurgical and Materials Transactions A: Physical Metallurgy and Materials Science · EID: 2-s2.0-23744481521
"Corrosion of candidate materials for supercritical water-cooled reactors" [2005] Proceedings of the Twelfth International Conference on Environmental Degradation of Materials in Nuclear Power Systems-Water Reactors · EID: 2-s2.0-33745200046
"Effects of methane plasma ion implantation on the microstructure and wear resistance of NiTi shape memory alloys" W.C. Crone, L. Tan, [2005] Thin Solid Films · DOI: 10.1016/j.tsf.2004.06.151 · EID: 2-s2.0-9944233059
"Effects of oxygen ion implantation on wear behavior of NiTi shape memory alloy" G. Shaw, K. Sridharan, W.C. Crone, L. Tan, [2005] Mechanics of Materials · DOI: 10.1016/j.mechmat.2005.04.001 · EID: 2-s2.0-20344388075
"Multiphase equilibria in the metal-rich region of the Mo-Ti-Si-B system: Thermodynamic prediction and experimental validation" Y.A. Chang, L. Tan, W. Cao, Y. Yang, [2005] Acta Materialia · DOI: 10.1016/j.actamat.2004.12.020 · EID: 2-s2.0-13844256840
"Thermodynamic modeling and experimental investigation of the Ti-rich corner of the Ti-Si-B system" Y.A. Chang, L. Tan, Y. Yang, [2005] Intermetallics · DOI: 10.1016/j.intermet.2005.02.001 · EID: 2-s2.0-21344456733
"Corrosion behavior of candidate alloys for supercritical water reactors" [2004] Proceedings of the 2004 International Congress on Advances in Nuclear Power Plants, ICAPP'04 · EID: 2-s2.0-14844285472
"In situ TEM observation of two-step martensitic transformation in aged NiTi shape memory alloy" W.C. Crone, L. Tan, [2004] Scripta Materialia · DOI: 10.1016/j.scriptamat.2003.12.019 · EID: 2-s2.0-0346640516
"Corrosion and wear-corrosion behavior of NiTi modified by plasma source ion implantation" L Tan, [2003] Biomaterials · DOI: 10.1016/s0142-9612(03)00271-0 · EID: 2-s2.0-0037482961
"Experimental investigation and thermodynamic descriptions of the Mo-Si-Ti system" Y.A. Chang, L. Tan, Y. Du, Y. Yang, [2003] Materials Science and Engineering A · DOI: 10.1016/s0921-5093(03)00560-4 · EID: 2-s2.0-0142057274
"Phase diagram of the Nb-Al-Si ternary system" L.A Peluso, M.R Jackson, Lizhen Tan, J.-C Zhao, [2003] Journal of Alloys and Compounds · DOI: 10.1016/s0925-8388(03)00524-3 · EID: 2-s2.0-0141568051
"Fretting wear study of surface modified Ni-Ti shape memory alloy" W. C. Crone, K. Sridharan, L. Tan, [2002] Journal of Materials Science: Materials in Medicine · DOI: 10.1023/a:1014735225436 · EID: 2-s2.0-0036233626
"Surface characterization of NiTi modified by plasma source ion implantation" W.C. Crone, L. Tan, [2002] Acta Materialia · DOI: 10.1016/s1359-6454(02)00251-3 · EID: 2-s2.0-0037190949
"The 773 K isothermal section of Er-Ni-Sb phase diagram" Lizhen Tan, Lingmin Zeng, [2002] Journal of Alloys and Compounds · DOI: 10.1016/s0925-8388(02)00522-4 · EID: 2-s2.0-0037131836
"Plateau effect of CuZnAl memory elements" [2001] Zhongguo Youse Jinshu Xuebao/Chinese Journal of Nonferrous Metals · EID: 2-s2.0-0035365997
Source: ORCID/CrossRef using DOI
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NSUF Supported Research

Correlation between Microstructure and Mechanical Properties of Neutron-Irradiated Ferritic-Martensitic and Austenitic Steels - FY 2017 CINR, #17-13050

Morphological Response of Spherical and Platelet MX-Type Precipitates to In-Situ Ion Irradiation in Novel Fe-Based Alloys - FY 2020 RTE 2nd Call, #20-4200

Radiation-Hardening and Microstructural Stability of NF709 Austenitic Stainless Steel - FY 2017 RTE 1st Call, #17-728

Stability of Precipitates under Ion Irradiation - FY 2012 RTE Solicitation, #12-373
NSUF Research Collaborations

Radiation effect to the deformation mechanism of Alloys 800H and 800H-TMP - FY 2020 RTE 2nd Call, #20-4094

Atom Probe Tomography Investigation on the Precipitation of Neutron-Irradiated Alloy 800H/800H-TMP - FY 2019 RTE 2nd Call, #19-1734

Local Deformation Mechanism of Neutron-Irradiated NF709 Austenitic Stainless Steel - FY 2019 RTE 1st Call, #19-1652

Radiation-Hardening and Microstructural Stability of NF709 Austenitic Stainless Steel - FY 2017 RTE 3rd Call, #17-1014

Investigation of Deformation Mechanisms of an Intermetallic-strengthened Alloy with and without Heavy Ion Irradiation - FY 2017 RTE 1st Call, #16-804

Characterize Neutron Irradiated NF709 Stainless Steel Using Atom Probe Tomography - FY 2015 RTE 3rd Call, #15-591

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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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