Article
Engineering, Mechanical
Zhijie Li, Zhanli Liu, Zhuo Zhuang, Yinan Cui
Summary: Tungsten, as the plasma-facing material in nuclear fusion devices, exhibits plasticity with strong temperature dependence and non-Schmid effect, but the influence of these features on irradiated tungsten behavior is not well understood. A crystal plasticity model has been developed to study this, showing that post-irradiation mechanical tests at room temperature may underestimate deformation localization, while thermal-activated dislocation mobility in low temperatures may lead to short-term deformation without clear dislocation channels.
INTERNATIONAL JOURNAL OF PLASTICITY
(2021)
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
Materials Science, Multidisciplinary
Keyou S. Mao, Aaron J. French, Xiang Liu, Yaqiao Wu, Lucille A. Giannuzzi, Cheng Sun, Megha Dubey, Paula D. Freyer, Jonathan K. Tatman, Frank A. Garner, Lin Shao, Janelle P. Wharry
Summary: This study investigates the integrity of laser welds on neutron irradiated, He-containing steels. Laser welding nearly eliminates all irradiation-induced cavities and suppresses He-induced cracking. Laser welding induces Cr-rich precipitation and suppresses grain boundary radiation-induced segregation.
MATERIALS & DESIGN
(2021)
Article
Materials Science, Multidisciplinary
Yinan Cui, Nasr Ghoniem, Giacomo Po
Summary: This study reviewed recent work on plastic deformation in irradiated materials at the nano- and micro scales using Discrete Dislocation Dynamics (DDD) simulations. The simulations provided new insights into collective dislocation-irradiation defect interactions, as well as the temporal and spatial characteristics associated with plastic instabilities. The development of theoretical models and probability models advanced the understanding of plastic flow localization in irradiated materials for the design of future radiation-resistant materials.
JOURNAL OF NUCLEAR MATERIALS
(2021)
Article
Materials Science, Multidisciplinary
Donghai Du, Kai Sun, Gary S. Was
Summary: The study showed that neutron irradiation affects the stress corrosion crack initiation of 304L stainless steel, but the dependency on dose is slight. Grain boundary oxidation was observed prior to crack initiation, with cracks predominantly initiating at DC-GB intersections.
Article
Engineering, Mechanical
Bing Wang, Qian Wang, Rong Luo, Qianhua Kan, Bin Gu
Summary: The creep deformation behavior and mechanisms of nanocrystalline 316L austenitic stainless steels at high temperature are investigated using molecular dynamics simulations with different peak stresses. The results show that the creep deformation is caused by the interaction among dislocations, diffusion in the grains' interior and grain boundaries, and sliding of grain boundaries. Diffusion in the grains' interior and grain boundaries, as well as sliding of grain boundaries, are the dominant mechanisms during the initial and steady-state creep stages. Dislocation slipping becomes the main mechanism during the accelerated creep stage after some grain boundaries are destroyed. This study provides a fundamental understanding of the creep mechanisms of nanocrystalline 316L austenitic stainless steel, which can guide the design and fabrication of enhanced creep-resistant alloys.
ACTA MECHANICA SINICA
(2023)
Article
Materials Science, Multidisciplinary
J. Hure, A. Courcelle, I. Turque
Summary: Swelling is commonly observed in austenitic stainless steels irradiated at high doses and high temperatures, and it can lead to macroscopic embrittlement. This study presents an experimental database and theoretical analysis to investigate the fatigue mechanisms induced by swelling and the effects of structural factors. The results provide insights into the mechanical perspective of swelling-induced embrittlement.
JOURNAL OF NUCLEAR MATERIALS
(2022)
Article
Materials Science, Multidisciplinary
M. Shreevalli, Ran Vijay Kumar, Divakar Ramachandran, C. Padmaprabu, V Karthik, Archna Sagdeo
Summary: The microstructural changes induced by neutron irradiation in different variants of austenitic stainless steels were characterized using the ADXRD technique. The effect of irradiation-induced defects on X-ray diffraction peak profile parameters was quantified and correlated with dislocation density. Peak broadening increased with increasing displacement damage levels in most cases. Lattice contraction was observed in SS 304 L(N) and SS 316, while lattice expansion was exhibited in SS 316 L(N). The increase in yield strength was related to the dislocation density, with saturation observed in SS 304 L(N) and linear behavior in SS 316 L(N).
JOURNAL OF NUCLEAR MATERIALS
(2023)
Article
Materials Science, Multidisciplinary
Masayoshi Kumagai, Masatoshi Kuroda, Takashi Matsuno, Stefanus Harjo, Koichi Akita
Summary: This study investigated the stress response of austenitic stainless steel using neutron diffraction and found that there is stress sharing between austenite and martensite. The actual stress in the martensite is about half of the assumed stress and the phase stress in the austenite, and the martensite contains a large compressive residual stress.
MATERIALS & DESIGN
(2022)
Article
Chemistry, Physical
Malcolm Griffiths
Summary: Austenitic stainless steels are crucial materials used for core internal structures in nuclear reactors due to their high strength and toughness after irradiation. Understanding and predicting the changes in mechanical properties and dimensional stability over extended periods of operation is essential for the ongoing operability of reactors operating at different temperatures.
Article
Materials Science, Multidisciplinary
Nitish Bibhanshu, Maxim N. Gussev, Thomas M. Rosseel
Summary: The deformation mechanisms of neutron-irradiated 304 L stainless steel were investigated using the in-situ electron backscattered diffraction (EBSD) technique. Comparative analysis with non-irradiated samples showed that the irradiated samples had higher fractions of slip bands even at low amounts of deformation. Additionally, formation of twins and martensite in the neutron-irradiated samples was found to be almost parallel to the slip bands.
MATERIALS CHARACTERIZATION
(2021)
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
M. N. Gussev, D. A. McClintock, T. G. Lach
Summary: Luders-type propagating deformation bands were observed in irradiated 316L stainless steel samples, and their formation was found to be related to the appearance and evolution of defect-free channels.
Article
Materials Science, Multidisciplinary
Hongzhuang Zhang, Mengtao Xu, Zhendong Liu, Changyou Li, Yimin Zhang
Summary: The stored energy induced by SLM process and cyclic strain during fatigue testing can trigger grain boundary migration and local recrystallization behavior, impacting the fatigue performance of stainless steel. Understanding the role of local recrystallization in fatigue failure mechanisms of additively manufactured materials is essential for further research and development in this field.
MATERIALS CHARACTERIZATION
(2021)
Article
Materials Science, Multidisciplinary
Koki Yamamoto, Toshio Ogawa, Zhilei Wang, Yoshitaka Adachi
Summary: In this study, scale-bridging analysis was conducted on the heterogeneous deformation behavior in SUS310S austenitic stainless steel using X-ray line profile analysis, digital image correlation (DIC), and transmission electron microscopy (TEM). The results showed that increasing strain led to higher dislocation density and smaller crystallite size, with different forms of dislocation distribution observed in different stages of deformation.
Article
Materials Science, Multidisciplinary
Kevin G. Field, Ying Yang, Todd R. Allen, Jeremy T. Busby
Article
Materials Science, Multidisciplinary
T. S. Byun, Y. Yang, N. R. Overman, J. T. Busby
Article
Materials Science, Multidisciplinary
L. Tan, R. E. Stoller, K. G. Field, Y. Yang, H. Nam, D. Morgan, B. D. Wirth, M. N. Gussev, J. T. Busby
Article
Materials Science, Multidisciplinary
L. Tan, J. T. Busby
JOURNAL OF NUCLEAR MATERIALS
(2015)
Article
Materials Science, Multidisciplinary
Keith J. Leonard, Maxim N. Gussev, Jacqueline N. Stevens, Jeremy T. Busby
JOURNAL OF NUCLEAR MATERIALS
(2015)
Article
Materials Science, Multidisciplinary
Ying Yang, Kevin G. Field, Todd R. Allen, Jeremy T. Busby
JOURNAL OF NUCLEAR MATERIALS
(2016)
Article
Materials Science, Multidisciplinary
L. Tan, J. T. Busby, P. J. Maziasz, Y. Yamamoto
JOURNAL OF NUCLEAR MATERIALS
(2013)
Article
Materials Science, Multidisciplinary
L. Tan, J. T. Busby, H. J. M. Chichester, K. Sridharan, T. R. Allen
JOURNAL OF NUCLEAR MATERIALS
(2013)
Article
Materials Science, Multidisciplinary
Kevin G. Field, Leland M. Barnard, Chad M. Parish, Jeremy T. Busby, Dane Morgan, Todd R. Allen
JOURNAL OF NUCLEAR MATERIALS
(2013)
Article
Materials Science, Multidisciplinary
L. Tan, T. R. Allen, J. T. Busby
JOURNAL OF NUCLEAR MATERIALS
(2013)
Article
Materials Science, Multidisciplinary
Kevin G. Field, Maxim N. Gussev, Jeremy T. Busby
JOURNAL OF NUCLEAR MATERIALS
(2014)
Article
Materials Science, Multidisciplinary
Y. Yang, J. T. Busby
JOURNAL OF NUCLEAR MATERIALS
(2014)
Article
Nanoscience & Nanotechnology
M. N. Gussev, J. T. Busby, T. S. Byun, C. M. Parish
MATERIALS SCIENCE AND ENGINEERING A-STRUCTURAL MATERIALS PROPERTIES MICROSTRUCTURE AND PROCESSING
(2013)
Article
Materials Science, Multidisciplinary
Mahmood Mamivand, Ying Yang, Jeremy Busby, Dane Morgan
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)