Article
Materials Science, Multidisciplinary
D. Terentyev, A. Zinovev, T. Khvan, J-H You, N. Van Steenberge, E. E. Zhurkin
Summary: Designing plasma-facing components (PFC) for DEMO divertor poses new challenges for in-vessel materials, with chromium (Cr) and Cr-W alloy being considered as candidate materials for structural bodies. Alloying shows potential for increasing work hardening capacity and fracture strength, and may improve materials' resistance to irradiation. Neutron irradiation results in degradation of mechanical properties, making all materials brittle at the applied temperature, with significant modifications observed in Cr-10at.%W alloy. Fracture surface analysis is conducted to understand the nature of brittle fracture and reasons for observed brittleness.
JOURNAL OF NUCLEAR MATERIALS
(2021)
Article
Chemistry, Physical
E. L. Sikorski, M. A. Cusentino, M. J. McCarthy, J. Tranchida, M. A. Wood, A. P. Thompson
Summary: Tungsten (W) is a preferred material for the divertor due to its properties, but it has limitations at high temperatures. Dispersion-strengthening W with zirconium carbide (ZrC) can improve its properties, but the effects of dispersoids at high temperatures are still unknown.
JOURNAL OF CHEMICAL PHYSICS
(2023)
Article
Physics, Fluids & Plasmas
E. Tsitrone, B. Pegourie, J. P. Gunn, E. Bernard, V Bruno, Y. Corre, L. Delpech, M. Diez, D. Douai, A. Ekedahl, N. Fedorczak, A. Gallo, T. Loarer, S. Vartanian, J. Gaspar, M. Le Bohec, F. Rigollet, R. Bisson, S. Brezinsek, T. Dittmar, G. De Temmerman, A. Hakola, T. Wauters, M. Balden, M. Mayer
Summary: In this study, a helium experiment was conducted in the full tungsten WEST tokamak, revealing the conditions for tungsten fuzz formation in the outer strike point area of the tungsten divertor elements. Preliminary inspection showed no visible signs of surface modification, but significant net erosion was observed in this area.
Article
Nuclear Science & Technology
A. Durif, M. Richou, J. -M. Bergheau, Y. Corre, M. Diez, P. Reilhac, J. P. Gunn, E. Tsitrone
Summary: This study investigates the cracking issue of the plasma-facing units (PFUs) in the WEST tokamak through experiments and numerical simulations. The research finds that cracks occur in the PFUs during the fusion reaction process and these cracks exhibit certain regularity. Based on the experimental results and numerical simulations, the researchers determine the mechanism of crack generation and the pattern of crack propagation, providing deeper understanding of the damage process of the PFUs.
FUSION ENGINEERING AND DESIGN
(2023)
Article
Physics, Multidisciplinary
Y. Corre, A. Grosjean, J. P. Gunn, K. Krieger, S. Ratynskaia, O. Skalli-Fettachi, C. Bourdelle, S. Brezinsek, V Bruno, N. Chanet, J. Coenen, X. Courtois, R. Dejarnac, E. Delmas, L. Delpech, C. Desgranges, M. Diez, L. Dubus, A. Durif, A. Ekedahl, N. Fedorczak, M. Firdaouss, J-L Gardarein, J. Gaspar, J. Gerardin, C. Guillemaut, M. Houry, T. Loarer, P. Maget, P. Mandelbaum, R. Mitteau, M. Missirlian, P. Moreau, R. Nouailletas, E. Nardon, C. Pocheau, A. Podolnik, P. Reilhac, X. Regal-Mezin, C. Reux, M. Richou, F. Rigollet, J-L Schwob, E. Thoren, P. Tolias, E. Tsitrone
Summary: The controlled and sustained tungsten melting experiment on an ITER-like plasma facing unit (PFU) was successfully conducted in WEST, with no noticeable impact on plasma operation. This involved exposing the leading edge to a high heat flux for up to 5 seconds, resulting in material displacement and excavation depth of about 230 µm.
Article
Chemistry, Physical
Zhuoxin Li, Yulin Zhang, Hong Li, Yipeng Wang, Lijuan Wang, Yu Zhang
Summary: This work investigated the liquation cracking susceptibility of aluminum alloy 7075-T651 joints welded using customized Al-Cu-Si and Al-Cu-Mg-Zn filler wire during gas tungsten arc welding. The results showed that the use of different filler metals resulted in varying liquation cracking susceptibility. Mechanical testing demonstrated that eliminating liquation cracks can reduce the data dispersion of the 7075 gas tungsten arc welding joint.
Article
Physics, Fluids & Plasmas
D. Zhu, Z. Guo, C. Xuan, B. Yu, C. Li, B. Gao, R. Ding, R. Yan, Y. Wang, C. He, D. Yao, L. Cao, P. Zi, L. Han, B. Wang, W. Fu, Y. Li, J. Chen
Summary: Tungsten is a highly promising plasma-facing material for fusion devices, but it faces the risk of melting under extremely high heat fluxes. In the EAST tokamak, actively cooled tungsten plasma-facing components (PFCs) with monoblocks and flat-type structures have been installed and their damage mechanisms have been compared. Severe melting and exfoliation were observed on W/Cu flat-type components, causing disruptions and deterioration of plasma performance. Melting was also found on the sharp edges of W/Cu monoblocks, but with improvements compared to the upper divertor. The experiences from using both types of PFCs provide important lessons for future fusion device design and optimization.
Article
Materials Science, Multidisciplinary
A. E. Zhdanov, M. S. Syrtanov, N. E. Kurdyumov, T. L. Murashkina
Summary: The paper presents the characterization of the structure and sorption properties of Ti21.5V40Cr38.5 alloy synthesized by abnormal glow discharge plasma melting and arc melting. X-ray diffraction analysis revealed the presence of the main TiVCr phase with a body-centered cubic lattice and the Ti2O phase with a hexagonal close-packed lattice. The maximum hydrogen capacity of the samples synthesized by abnormal glow discharge plasma melting after 3 cycles was 3 wt%.
Article
Materials Science, Multidisciplinary
Yassar E. Mukhrish, Muhammad Asad, Muhammad Azhar Ali Khan, Faramarz Djavanroodi
Summary: This research investigates the use of an automated cladding welding machine for wire arc additive manufacturing (WAAM) of a semi-cylindrical part. The study aims to evaluate the mechanical properties and microstructure of the manufactured part, as well as any potential changes in the properties of the employed Nickel wire. The results show that the hardness of the material is higher than the original wire, and the tensile and yield strengths are lowest in the direction across the thickness. The microstructure analysis reveals a high level of ductility in both parallel and perpendicular orientations to the deposition direction. This confirms the feasibility of using additive manufacturing for this super-alloy material without significant changes in its mechanical properties, with room for improvement by optimizing machine parameters.
MECHANICS OF ADVANCED MATERIALS AND STRUCTURES
(2023)
Article
Physics, Fluids & Plasmas
M. Diez, Y. Corre, E. Delmas, N. Fedorczak, M. Firdaouss, A. Grosjean, J. P. Gunn, T. Loarer, M. Missirlian, M. Richou, E. Tsitrone
Summary: After the first phase of operation of the WEST tokamak, it was found that tungsten coatings are generally in good condition but prone to delamination in certain areas; following the experimental campaigns, tungsten-coated carbon tiles were replaced by bulk tungsten tiles, and damage on the bulk tungsten ITER-like components was mainly due to exposure to parallel heat flux rather than continuous heating.
Article
Nuclear Science & Technology
Dirk Naujoks, Chandra-Prakash Dhard, Yuhe Feng, Yu Gao, Torsten Stange, Birger Buttenschoen, Sergey A. Bozhenkov, Sebastijan Brezinsek, Kai Jakob Brunner, Gabor Cseh, Andreas Dinklage, David Ennis, Joris Fellinger, Eric Flom, Dorothea Gradic, Eduard Grigore, Dirk Hartmann, Frederik Henke, Marcin Jakubowski, Amit Kharwandikar, Mikhail Khokhlov, Jens Knauer, Gabor Kocsis, Petra Kornejew, Maciej Krychowiak, Matej Mayer, Paul McNeely, Daniel Medina, Rudolf Neu, Kian Rahbarnia, Cristian Ruset, Norbert Rust, Peter Scholz, Thomas Sieber, Ivan Stepanov, Naoki Tamura, Erhui Wang, Thomas Wegner, Daihong Zhang
Summary: The transition to reactor-relevant materials for the plasma facing components is a crucial step to demonstrate the feasibility of the stellarator concept for future fusion reactors. Tungsten was used as the plasma-facing material in W7-X stellarator, and design changes were made to improve the overheating issue in the baffle area.
NUCLEAR MATERIALS AND ENERGY
(2023)
Article
Chemistry, Physical
Yaping Bai, Keke Tian, Jianping Li, Zhong Yang
Summary: In this study, Fe-25Mn-9Al-8Ni-1C-xTi alloy with different titanium contents was prepared and studied for microstructure and oxidation behavior at 600 degrees C. The results showed that increasing titanium content reduced oxidation weight gain at initial stage but showed a trend of first increasing then decreasing with extended oxidation time. The alloy exhibited a double-layer oxide structure with dense manganese and aluminum oxides in the inner layer.
Article
Materials Science, Multidisciplinary
X. C. Meng, L. Li, C. L. Li, D. Andruczyk, K. Tritz, R. Maingi, M. Huang, D. H. Zhang, W. Xu, Z. Sun, G. Z. Zuo, J. S. Hu
Summary: The corrosion behaviors of molybdenum and a molybdenum-based alloy in liquid lithium were investigated. Molybdenum exhibited uniform corrosion, while the alloy showed nonuniform corrosion with preferential grain boundary attack. The corrosion resistance of the alloy was affected by elements such as carbon, nitrogen, zirconium, and titanium in the liquid lithium.
Article
Materials Science, Multidisciplinary
Xinyun Duan, Yufeng Huang, Wenyang Liu, Qingshan Cai, Wensheng Liu, Yunzhu Ma
Summary: In this study, W-xTa alloys with different Ta contents were fabricated using the arc-melting method, and the effects of Ta on the microstructure and mechanical properties of the alloys were investigated. The results showed that the addition of Ta could refine the grain size of W alloys and improve their hardness and strength, achieving the best comprehensive mechanical properties.
MATERIALS CHARACTERIZATION
(2022)
Article
Spectroscopy
Huace Wu, Ding Wu, Cong Li, Longfei Li, Xue Bai, Xiaohan Hu, Zhonglin He, Yan Lyu, Ran Hai, Hongbin Ding
Summary: Real-time acquisition of dynamic information on the surface elemental composition of the first wall is crucial for understanding plasma-wall interaction and optimizing experimental conditions in a tokamak. The effect of laser ablation angles (LAAs) on the in-situ laser-induced breakdown spectroscopy (LIBS) system on the EAST upper divertor was evaluated. LIBS experiments were conducted with variable LAAs on tungsten, molybdenum, and copper samples, and their ablation depth and mass were measured. The results showed that larger LAAs improved the depth resolution of LIBS and provided valuable insights for depth-profiling analysis.
SPECTROCHIMICA ACTA PART B-ATOMIC SPECTROSCOPY
(2023)
Article
Materials Science, Multidisciplinary
D. Terentyev, J. Riesch, S. Lebediev, T. Khvan, A. Zinovev, M. Rasinski, A. Dubinko, J. W. Coenen
INTERNATIONAL JOURNAL OF REFRACTORY METALS & HARD MATERIALS
(2018)
Article
Materials Science, Multidisciplinary
D. Terentyev, J. Riesch, S. Lebediev, T. Khvan, A. Dubinko, A. Bakaeva
INTERNATIONAL JOURNAL OF REFRACTORY METALS & HARD MATERIALS
(2018)
Article
Nuclear Science & Technology
D. Terentyev, J. Riesch, A. Dubinko, T. Khvan, E. E. Zhurkin
FUSION ENGINEERING AND DESIGN
(2019)
Article
Materials Science, Multidisciplinary
D. Terentyev, W. Van Renterghem, L. Tanure, A. Dubinko, J. Riesch, S. Lebediev, T. Khvan, K. Verbeken, J. W. Coenen, E. E. Zhurkin
INTERNATIONAL JOURNAL OF REFRACTORY METALS & HARD MATERIALS
(2019)
Article
Chemistry, Multidisciplinary
Ana Ruiz-Moreno, Peter Hahner, Lukasz Kurpaska, Jacek Jagielski, Philippe Spatig, Michal Trebala, Simo-Pekka Hannula, Susana Merino, Gonzalo de Diego, Hygreeva Namburi, Ondrej Libera, Dimitry Terentyev, Tymofii Khvan, Cornelia Heintze, Nigel Jennett
Article
Materials Science, Multidisciplinary
G. Bonny, M. J. Konstantinovic, A. Bakaeva, C. Yin, N. Castin, K. Mergia, V Chatzikos, S. Dellis, T. Khvan, A. Bakaev, A. Dubinko, D. Terentyev
Article
Materials Science, Multidisciplinary
G. Bonny, T. Khvan, A. Bakaeva, C. Yin, A. Dubinko, C. Cabet, M. Loyer-Prost, N. Castin, A. Bakaev, D. Terentyev
Summary: Different methods were used to analyze the effects of tungsten self-ion irradiation on radiation hardening, and a satisfactory analysis procedure was established, leading to the discovery that radiation hardening saturates above 0.1 dpa.
JOURNAL OF NUCLEAR MATERIALS
(2021)
Article
Chemistry, Multidisciplinary
Lyubomira Veleva, Peter Hahner, Andrii Dubinko, Tymofii Khvan, Dmitry Terentyev, Ana Ruiz-Moreno
Summary: This study investigates the effects of pre-straining on the mechanical properties of iron through nanoindentation, revealing increased pile-up formation and discrepancies between hardness measurements and tensile test results. The presence of carbon interstitial impurities at 125 degrees C is found to affect the strain hardening behavior and nano-hardness results.
Article
Materials Science, Multidisciplinary
T. Khvan, L. Noels, D. Terentyev, F. Dencker, D. Stauffer, U. D. Hangen, W. Van Renterghem, C. Cheng, A. Zinovev
Summary: The application of reduced activation ferritic/martensitic (RAFM) steels in future fusion reactors requires an understanding of their mechanical properties under relevant operational conditions. Experimental and computational methods are used to simplify the characterization of irradiated materials, with ion irradiation considered as a possible alternative to high-flux neutron irradiation damage. Nanoindentation techniques and crystal plasticity finite element method (CPFEM) were used to study BCC iron, the basis material for ferritic steels, and analyze its mechanical behavior.
JOURNAL OF NUCLEAR MATERIALS
(2022)
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)