Article
Materials Science, Multidisciplinary
Dayu Fajrul Falaakh, Patrick Myers, Jae Phil Park, Gary S. Was, Chi Bum Bahn
Summary: This paper presents a statistical analysis of the IASCC initiation data for 304 and 316 stainless steels. The stress threshold for IASCC initiation was determined, and survival analysis revealed significant covariates such as stress level, neutron dose, and component. The failure rate was found to increase with increasing stress level and neutron dose, and FTT materials had higher failure rates than BFB materials.
JOURNAL OF NUCLEAR MATERIALS
(2023)
Article
Materials Science, Multidisciplinary
J. Tabin, K. Nalepka, J. Kawalko, A. Brodecki, P. Bala, Z. Kowalewski
Summary: A remarkable plastic flow instability is observed during tensile deformation of the commercial 304 stainless-steel sheet at room temperature. The occurrence of plastic flow instability in 304 is dependent on the strain rate and specimen gage length. Moreover, the enhanced strain hardening resulting from deformation-induced martensitic transformation facilitates the orderly propagation of the strain-localized band.
METALLURGICAL AND MATERIALS TRANSACTIONS A-PHYSICAL METALLURGY AND MATERIALS SCIENCE
(2023)
Article
Materials Science, Multidisciplinary
Josef Nemec, Lenka Kuncicka, Petr Opela, Karel Dvorak
Summary: Austenitic stainless steels, including ChN35VT steel, have wide application potential in various fields, such as the nuclear power industry. This study experimentally characterized the deformation behavior of ChN35VT steel under hot conditions and compared it with 08Ch18N10T steel. The results showed that ChN35VT steel exhibited significantly higher flow stress values.
Article
Nanoscience & Nanotechnology
Zhitao Wu, Kaiyu Zhang, Chengshuang Zhou, Zhengrong Zhou, Wenli Zhang, Fan Bao, Jinyang Zheng, Lin Zhang
Summary: The study found that the fatigue crack growth rate of 304 and 316 stainless steels is influenced by the deformation temperature in hydrogen and argon atmospheres, especially warm deformation can improve hydrogen embrittlement resistance.
MATERIALS SCIENCE AND ENGINEERING A-STRUCTURAL MATERIALS PROPERTIES MICROSTRUCTURE AND PROCESSING
(2021)
Article
Nanoscience & Nanotechnology
Minghao Huang, Lingyu Wang, Sen Yuan, Jinliang Wang, Chenchong Wang, Anna Mogucheva, Wei Xu
Summary: This study developed a novel processing route consisting of inhomogeneous rolling and annealing to fabricate a large gradient profile in the austenite grain size. The fabricated bulk gradient austenitic steel exhibited higher tensile strength and Charpy impact energy compared with the uniform-grain-size structural steel. The deformation mechanisms of the bulk gradient austenitic steel were explored, revealing the combined contribution of hetero-deformation induced strengthening and transformation-induced plasticity effect.
MATERIALS SCIENCE AND ENGINEERING A-STRUCTURAL MATERIALS PROPERTIES MICROSTRUCTURE AND PROCESSING
(2022)
Article
Materials Science, Multidisciplinary
Xiangyu Wang, Yangting Sun, Pei He, Xin Tan, Qingyuan Zhou, Wenbo Wu, Chenxi Lv, Jin Li, Yiming Jiang
Summary: This study investigates the distinct pitting behavior between the fusion zones of QN2109 and 317 L laser welds. It is found that the segregation of Mn in the two fusion zones differs due to composition and cooling rate variations, resulting in different corrosion behaviors.
Article
Materials Science, Multidisciplinary
Xiangyu Wang, Yangting Sun, Pei He, Xin Tan, Qingyuan Zhou, Wenbo Wu, Chenxi Lv, Jin Li, Yiming Jiang
Summary: The distinct pitting behavior between the fusion zone of QN2109 laser welds and that of 317 L is due to differences in composition and cooling rate, leading to different segregation of Mn. Both welds have residual 6-ferrite, with QN2109 having higher content. The pitting initiation sites also differ, with QN2109 producing secondary austenite prone to pitting and M23C6 being dissolved in the fusion zone of 317 L, significantly reducing the number of pitting sites.
Article
Materials Science, Multidisciplinary
Litao Chang, M. Grace Burke, Kudzanai Mukahiwa, Jonathan Duff, YongLiang Wang, Fabio Scenini
Summary: Cold-worked Type 304L/316L stainless steel specimens with varying martensite content were tested in high-temperature hydrogenated water to understand the role of martensite on stress corrosion crack initiation. The results showed that cold-rolled 304L with martensite required higher strain to induce SCC initiation compared to other cold-worked stainless steels. Mechanisms responsible for the different SCC initiation susceptibilities were discussed based on experimental observations.
Review
Engineering, Manufacturing
Decheng Kong, Chaofang Dong, Shaolou Wei, Xiaoqing Ni, Liang Zhang, Ruixue Li, Li Wang, Cheng Man, Xiaogang Li
Summary: Additive manufacturing technology offers significant advantages in tailored design of structural components, with sub-micro cellular structures having substantial effects on engineering properties. By focusing on AM austenitic stainless steel as a model material, research has explored the formation mechanisms, kinetics, growth orientation, and stability of these cellular structures. The correlation between cellular microstructure and mechanical properties, as well as corrosion responses, is a key area of concern for advancing high-performance structural alloy development in additive manufacturing.
ADDITIVE MANUFACTURING
(2021)
Article
Nanoscience & Nanotechnology
Rui Ke, Xiangliang Wan, Yongjie Zhang, Chengyang Hu, Kaiming Wu
Summary: This study investigates the impact of annealing temperature on the microstructure and mechanical properties of reversion-induced, fine grain strengthened austenitic stainless steels. The results showed that annealing at different temperatures led to different microstructural evolutions. Reversion of deformation-induced martensite occurred through a combination of diffusion and shear mechanisms at 700 degrees C, while occurring solely through a shear mechanism at 1000 degrees C. The resulting microstructures had a bimodal distribution at 700 degrees C and a unimodal distribution at 1000 degrees C. Tensile tests revealed that the specimens with a bimodal structure exhibited higher plasticity.
MATERIALS SCIENCE AND ENGINEERING A-STRUCTURAL MATERIALS PROPERTIES MICROSTRUCTURE AND PROCESSING
(2022)
Article
Materials Science, Multidisciplinary
Kyung-Shik Kim, Jee-Hyun Kang, Sung-Joon Kim
Summary: The study revealed that carbon can alleviate the impact of hydrogen on the tensile properties of stainless steel, but increasing the carbon content does not significantly affect hydrogen diffusivity. Cracks induced by hydrogen mainly occur at grain boundaries and propagate inside grains, but are suppressed by grain boundaries.
Article
Nanoscience & Nanotechnology
Yeonggeun Cho, Hojun Gwon, Sung-Joon Kim
Summary: In 15Cr-15Mn-4Ni austenitic stainless steels containing 0.1-0.3 wt% of either C or N, the effect of interstitial C and N atoms on high-temperature deformation behavior was investigated. It was found that N-added steels exhibited higher strength at a wide range of temperatures compared to C-added steels due to the stronger interaction between N atoms and grain boundaries, which led to relatively retarded dynamic recrystallization in the +N-steels.
MATERIALS SCIENCE AND ENGINEERING A-STRUCTURAL MATERIALS PROPERTIES MICROSTRUCTURE AND PROCESSING
(2021)
Article
Materials Science, Multidisciplinary
Lin Wang, Chen Chen, Zhuoyuan Li, Zhuyu Wang, Bo Lv, Fucheng Zhang
Summary: The hot compression of a super austenitic stainless steel was conducted at different temperatures under various angles between the solidification direction of columnar crystals and loading direction, revealing significant effects on microstructural evolution. Different dynamic recrystallization mechanisms were observed at different temperatures and angles, indicating the importance of crystal orientation in the recrystallization process.
JOURNAL OF MATERIALS RESEARCH AND TECHNOLOGY-JMR&T
(2021)
Article
Mechanics
P. Fernandez-Pison, J. A. Rodriguez-Martinez, E. Garcia-Tabares, I Aviles-Santillana, S. Sgobba
Summary: This paper characterizes the microstructural evolution, plastic flow, and fracture behaviors of AISI 304L and AISI 316LN stainless steels at extremely low temperatures. It demonstrates that the martensitic transformation in AISI 304L occurs faster and to a greater extent than in AISI 316LN at both 77 K and 4 K. Additionally, experimental results reveal that AISI 316LN displays higher fracture toughness than AISI 304L.
ENGINEERING FRACTURE MECHANICS
(2021)
Article
Metallurgy & Metallurgical Engineering
Zheng Chun, Liu Jiabin, Jiang Laizhu, Yang Cheng, Jiang Meixue
Summary: The microstructures, strengthening mechanisms, and corrosion resistances of nitrogen-alloyed QN1803 stainless steel and conventional 304 stainless steel under tensile deformation were studied. It was found that QN1803 stainless steel has a higher yield strength and slightly lower elongation, while the pitting and sulfuric acid corrosion resistances of 304 stainless steel are significantly reduced. Nitrogen alloying in stainless steel has important implications in industrial applications.
ACTA METALLURGICA SINICA
(2022)
Article
Materials Science, Multidisciplinary
E. Getto, K. Sun, A. M. Monterrosa, Z. Jiao, M. J. Hackett, G. S. Was
JOURNAL OF NUCLEAR MATERIALS
(2016)
Article
Materials Science, Multidisciplinary
C. D. Judge, V. Bhakhri, Z. Jiao, R. J. Klassen, G. Was, G. A. Botton, M. Griffiths
JOURNAL OF NUCLEAR MATERIALS
(2017)
Article
Materials Science, Multidisciplinary
A. Reichardt, A. Lupinacci, D. Frazer, N. Bailey, H. Vo, C. Howard, Z. Jiao, A. M. Minor, P. Chou, P. Hosemann
JOURNAL OF NUCLEAR MATERIALS
(2017)
Article
Instruments & Instrumentation
G. S. Was, S. Taller, Z. Jiao, A. M. Monterrosa, D. Woodley, D. Jennings, T. Kubley, F. Naab, O. Toader, E. Uberseder
NUCLEAR INSTRUMENTS & METHODS IN PHYSICS RESEARCH SECTION B-BEAM INTERACTIONS WITH MATERIALS AND ATOMS
(2017)
Article
Instruments & Instrumentation
Stephen Taller, David Woodley, Elizabeth Getto, Anthony M. Monterrosa, Zhijie Jiao, Ovidiu Toader, Fabian Naab, Thomas Kubley, Shyam Dwaraknath, Gary S. Was
NUCLEAR INSTRUMENTS & METHODS IN PHYSICS RESEARCH SECTION B-BEAM INTERACTIONS WITH MATERIALS AND ATOMS
(2017)
Article
Materials Science, Multidisciplinary
Z. Jiao, S. Taller, K. Field, G. Yeli, M. P. Moody, G. S. Was
JOURNAL OF NUCLEAR MATERIALS
(2018)
Article
Materials Science, Multidisciplinary
Z. Jiao, J. Hesterberg, G. S. Was
JOURNAL OF NUCLEAR MATERIALS
(2018)
Article
Materials Science, Multidisciplinary
Anthony M. Monterrosa, Zhijie Jiao, Gary S. Was
JOURNAL OF NUCLEAR MATERIALS
(2018)
Article
Materials Science, Multidisciplinary
Z. Jiao, J. Michalicka, G. S. Was
JOURNAL OF NUCLEAR MATERIALS
(2018)
Article
Nanoscience & Nanotechnology
Xiaodong Lin, Qunjia Peng, En-Hou Han, Wei Ke, Chen Sun, Zhijie Jiao
SCRIPTA MATERIALIA
(2018)
Article
Materials Science, Multidisciplinary
Nanjun Chen, Qing Peng, Zhijie Jiao, Isabella van Rooyen, William E. Skerjanc, Fei Gao
JOURNAL OF NUCLEAR MATERIALS
(2018)
Proceedings Paper
Materials Science, Multidisciplinary
Justin R. Hesterberg, Zhijie Jiao, Gary S. Was
PROCEEDINGS OF THE 18TH INTERNATIONAL CONFERENCE ON ENVIRONMENTAL DEGRADATION OF MATERIALS IN NUCLEAR POWER SYSTEMS - WATER REACTORS, VOL 2
(2018)
Proceedings Paper
Materials Science, Multidisciplinary
Yimeng Chen, Yan Dong, Emmanuelle Marquis, Zhijie Jiao, Justin Hesterberg, Gary Was, Peter Chou
PROCEEDINGS OF THE 18TH INTERNATIONAL CONFERENCE ON ENVIRONMENTAL DEGRADATION OF MATERIALS IN NUCLEAR POWER SYSTEMS - WATER REACTORS, VOL 2
(2018)
Article
Metallurgy & Metallurgical Engineering
Deng Ping, Peng Qunjia, Han En-Hou, Ke Wei, Sun Chen, Xia Haihong, Jiao Zhijie
ACTA METALLURGICA SINICA
(2017)
Article
Materials Science, Multidisciplinary
Ping Deng, Qunjia Peng, En-Hou Han, Wei Ke, Chen Sun, Zhijie Jiao
Article
Materials Science, Multidisciplinary
Liuming Wei, Jingwen Li, Yonggang Li, Qirong Zheng, Fan Cheng, Chuanguo Zhang, Jingyu Li, Gaofeng Zhao, Zhi Zeng
Summary: This study investigates the influence of He-V complexes on H behaviors on different W surfaces using DFT calculations. The results show that H dissolution is most difficult but H trapping is easiest on the W (110) surface, while the opposite is true on the W (111) surface. Moreover, the presence of He-V complexes increases the difficulty of H diffusion from bulk to surface and desorption.
JOURNAL OF NUCLEAR MATERIALS
(2024)
Article
Materials Science, Multidisciplinary
Yan Meng, Song Zeng, Chen Chen, Chaowen Zhu, Huahai Shen, Xiaosong Zhou, Xiaochun Han
Summary: The characteristics of magnetron sputtered Cr coatings vary with different temperature, bias voltage, and pressure. Coatings with random orientation, good crystallinity, and small grain size exhibit favorable oxidation behavior, while coatings with strong (200) texture, poor crystallinity, and large grains have many intrinsic defects that are detrimental to the protection property of the Cr coatings.
JOURNAL OF NUCLEAR MATERIALS
(2024)
Article
Materials Science, Multidisciplinary
Xinyuan Xu, Zefeng Yu, Wei-Ying Chen, Aiping Chen, Arthur Motta, Xing Wang
Summary: This study presents an automated approach for characterizing grain morphology in TEM images recorded during ion irradiation. By combining a machine learning model and a computer vision algorithm, comparable results to human analysis can be achieved with significantly reduced analysis time. Researchers can train their own models following the procedures described in this study to automate grain morphology analysis of their own TEM images.
JOURNAL OF NUCLEAR MATERIALS
(2024)
Article
Materials Science, Multidisciplinary
Shihao Wu, Dong Wang, Yapei Zhang, Koji Okamoto, Marco Pellegrini, Wenxi Tian, Suizheng Qiu, G. H. Su
Summary: The oxidation and degradation mechanisms of Cr coating on Zr alloy cladding under high temperature steam atmosphere are summarized, and a mathematical analysis model is established to predict the changes in coating thickness. The model is applied in the analysis of structure evolution under different conditions.
JOURNAL OF NUCLEAR MATERIALS
(2024)
Article
Materials Science, Multidisciplinary
V. Diaz-Mena, J. de Prado, M. Roldan, I. Izaguirre, M. Sanchez, M. Rieth, A. Urena
Summary: The brazeability of a cupronickel alloy was evaluated as a filler alloy for high-temperature joining of tungsten to steel. The study investigated the brazing conditions and the impact of the selected filler on the joint quality using numerical software. The results showed different metallurgical interactions and diffusion phenomena between the filler alloy and the base materials at different temperatures. The study emphasized the importance of selecting a suitable filler to mitigate residual stresses in the joints.
JOURNAL OF NUCLEAR MATERIALS
(2024)
Article
Materials Science, Multidisciplinary
Pengcheng Zhu, Yajie Zhao, Yan-Ru Lin, Jean Henry, Steven J. Zinkle
Summary: This study investigates the effect of heavy-ion irradiation on radiation hardening in high-purity binary alloy Fe18Cr. Nanoindentation testing and high-quality TEM imaging were conducted to extract hardness and microstructure information. The strength factor was accurately calculated based on the detailed TEM characterization of irradiated microstructures, and a refined hardening superposition method was applied to quantify the mechanical properties of ion-irradiated materials.
JOURNAL OF NUCLEAR MATERIALS
(2024)
Article
Materials Science, Multidisciplinary
Bin Wu, Haixia Ning, Hanzhen Zhu, Jianjun Chen, Kang Wang, Daiyu Zhang, Fu Wang, Qilong Liao
Summary: This study discusses the effects of ZrO2 and B2O3 on the phase composition and properties of SAP-based glass-ceramics. The results show that ZrO2 addition improves the formation of NZP phase while restricting the crystallization of AlPO4 phases. The correct ratios of ZrO2 and B2O3 allow only the formation of NZP phase within the SAP glass.
JOURNAL OF NUCLEAR MATERIALS
(2024)
Article
Materials Science, Multidisciplinary
Hwasung Yeom, Greg Johnson, Benjamin Maier, Tyler Dabney, Kumar Sridharan
Summary: Cr-Nb bilayer coatings were developed using cold spray deposition to improve the limiting operational temperature of Cr-coated Zr-alloy system. The coatings exhibited outstanding oxidation resistance at high temperatures and formed continuous intermetallic compound layers at the interfaces.
JOURNAL OF NUCLEAR MATERIALS
(2024)
Article
Materials Science, Multidisciplinary
Padhraic L. Mulligan, Andrew T. Nelson, Chad M. Parish, Patrick A. Champlin, Xiang Chen, Daniel Morrall, Jason M. Harp
Summary: Environmental barrier coatings are being developed to reduce oxidation and embrittlement in Zr-based materials. Chromium nitride is a candidate for this application, but understanding its impact on irradiation-induced creep and microstructure is critical.
JOURNAL OF NUCLEAR MATERIALS
(2024)
Article
Materials Science, Multidisciplinary
Dexuan Yan, Xinlei Cao, Ke Shen
Summary: This study investigated the purification mechanism of polycrystalline graphite by comparing IG-11 graphite with IG-110 nuclear grade graphite. The analysis revealed that metallic impurities in IG-11 were primarily segregated within graphite porosities, while IG-110 demonstrated a significant reduction in impurities. This research contributes to the development of innovative graphite purification techniques for greater purity and stronger oxidation resistance.
JOURNAL OF NUCLEAR MATERIALS
(2024)
Article
Materials Science, Multidisciplinary
Wei Xu, Wei Peng, Lei Shi, Qi Sun
Summary: This paper investigates the oxidation and shape evolution of matrix graphite in high temperature gas-cooled reactors during air-ingress accidents. A reaction kinetics model is established and computational fluid dynamics with a dynamic mesh method is used to simulate the oxidation process. The results show that the geometric shape of graphite changes significantly with increasing flow rate, and the graphite pebbles tend to form a structure with a narrow front and wide tail.
JOURNAL OF NUCLEAR MATERIALS
(2024)
Article
Materials Science, Multidisciplinary
Allison Harward, Casey Elliott, Michael Shaltry, Krista Carlson, Tae-Sic Yoo, Guy Fredrickson, Michael Patterson, Michael F. Simpson
Summary: This paper investigates the hygroscopic properties of eutectic LiCl-KCl absorbed into zeolite-4A. The study finds that water absorption and corrosion worsen with increasing salt loading. It also suggests that the salt can be stored in a non-inert atmosphere for a certain period of time.
JOURNAL OF NUCLEAR MATERIALS
(2024)
Article
Materials Science, Multidisciplinary
Takaaki Koyanagi, Xunxiang Hu, Christian M. Petrie, Gyanender Singh, Caen Ang, Christian P. Deck, Weon-Ju Kim, Daejong Kim, James Braun, Yutai Katoh
Summary: This study provides critical experimental data on the effects of irradiation on the hermeticity of SiC composite cladding, finding that irradiation can cause a decrease in hermeticity and cracking, and coating the outer surface can mitigate the cracking issue.
JOURNAL OF NUCLEAR MATERIALS
(2024)
Article
Materials Science, Multidisciplinary
S. Krat, A. Prishvitsyn, Yu. Gasparyan
Summary: This study proposes a probabilistic and diffusion-based model to describe the co-deposition of multiple hydrogen isotopes with slowly grown metal layers. The model calculates the relative concentrations of different hydrogen isotopes in the co-deposited metal layers. It is found that if hydrogen isotopes have different detrapping energies, only the isotope with the highest detrapping energy shows a monotonic decrease in concentration with deposition temperature. Furthermore, the study evaluates the uncertainty of tritium concentration in the co-deposited layer based on the uncertainty in detrapping energy of tritium and deuterium, predicting a >10% tritium concentration uncertainty for a 0.01 eV difference.
JOURNAL OF NUCLEAR MATERIALS
(2024)
Article
Materials Science, Multidisciplinary
Tijo Vazhappilly, Arup Kumar Pathak
Summary: This study investigates the effect of Ce atom substitution in UO2 on its thermophysical properties using density functional theory. The results show that the Ce substitution levels and the oxidation state of Ce/U atoms strongly influence the band structure and specific heat capacity of the UO2 lattice. These findings provide important insights into the fuel properties of UO2 under reactor conditions.
JOURNAL OF NUCLEAR MATERIALS
(2024)