☆ 4.7 Article

Comparison of hydrogen retention in W and W/Ta alloys

JOURNAL OF NUCLEAR MATERIALS (2012)

Journal

JOURNAL OF NUCLEAR MATERIALS

Volume 426, Issue 1-3, Pages 247-253

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ELSEVIER

DOI: 10.1016/j.jnucmat.2012.04.003

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Materials Science, Multidisciplinary Nuclear Science & Technology

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Abstract

The extreme brittleness of tungsten (W) is one of the challenges of using W as first wall material. One attempt to alleviate this problem is to use W alloys with better mechanical properties. However these alloying elements must not degrade the favorable properties of W with respect to its application at the first wall of fusion devices: low sputter yield and hydrogen inventory. In this work we investigate the hydrogen retention in the recently proposed W/Ta alloys under deuterium ion bombardment. By directly comparing pure W and W/Ta alloys with 1% and 5% Ta content we found that the W/Ta alloys retain significantly more hydrogen than pure W under identical implantation conditions. Our finding of increased hydrogen retention together with the fact that the Ta alloying did not improve the brittleness makes W/Ta alloys an unacceptable choice for the first wall of fusion devices. (C) 2012 Elsevier B.V. All rights reserved.

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MATERIALS (2020)

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Article Materials Science, Multidisciplinary

Hydrogen atom-ion synergy in surface lattice modification at sub-threshold energy

L. Gao, M. Wilde, A. Manhard, U. von Toussaint, W. Jacob

ACTA MATERIALIA (2020)

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Article Physics, Fluids & Plasmas

Progress from ASDEX Upgrade experiments in preparing the physics basis of ITER operation and DEMO scenario development

U. Stroth, D. Aguiam, E. Alessi, C. Angioni, N. Arden, R. Arredondo Parra, V Artigues, O. Asunta, M. Balden, V Bandaru, A. Banon-Navarro, K. Behler, A. Bergmann, M. Bergmann, J. Bernardo, M. Bernert, A. Biancalani, R. Bielajew, R. Bilato, G. Birkenmeier, T. Blanken, V Bobkov, A. Bock, T. Body, T. Bolzonella, N. Bonanomi, A. Bortolon, B. Boeswirth, C. Bottereau, A. Bottino, H. van den Brand, M. Brenzke, S. Brezinsek, D. Brida, F. Brochard, C. Bruhn, J. Buchanan, A. Buhler, A. Burckhart, Y. Camenen, B. Cannas, P. Cano Megias, D. Carlton, M. Carr, P. Carvalho, C. Castaldo, M. Cavedon, C. Cazzaniga, C. Challis, A. Chankin, C. Cianfarani, F. Clairet, S. Coda, R. Coelho, J. W. Coenen, L. Colas, G. Conway, S. Costea, D. Coster, T. Cote, A. J. Creely, G. Croci, D. J. Cruz Zabala, O. D'Arcangelo, G. Cseh, A. Czarnecka, I Cziegler, A. Dal Molin, P. David, C. Day, M. de Baar, P. de Marne, R. Delogu, S. Denk, P. Denner, A. Di Siena, J. J. Dominguez Palacios Duran, D. Dunai, A. Drenik, M. Dreval, R. Drube, M. Dunne, B. P. Duval, R. Dux, T. Eich, S. Elgeti, A. Encheva, K. Engelhardt, B. Erdos, I Erofeev, B. Esposito, E. Fable, M. Faitsch, U. Fantz, M. Farnik, H. Faugel, F. Felici, O. Ficker, S. Fietz, A. Figueredo, R. Fischer, O. Ford, L. Frassinetti, M. Froeschle, G. Fuchert, J. C. Fuchs, H. Fuenfgelder, S. Futatani, K. Galazka, J. Galdon-Quiroga, D. Gallart Escola, A. Gallo, Y. Gao, S. Garavaglia, M. Garcia Munoz, B. Geiger, L. Giannone, S. Gibson, L. Gil, E. Giovannozzi, S. Gloeggler, M. Gobbin, J. Gonzalez Martin, T. Goodman, G. Gorini, T. Gorler, D. Gradic, G. Granucci, A. Graeter, H. Greuner, M. Griener, M. Groth, A. Gude, L. Guimarais, S. Gunter, G. Haas, A. H. Hakola, C. Ham, T. Happel, N. den Harder, G. Harrer, J. Harrison, V Hauer, T. Hayward-Schneider, B. Heinemann, T. Hellsten, S. Henderson, P. Hennequin, A. Herrmann, E. Heyn, F. Hitzler, J. Hobirk, K. Hoefler, J. H. Holm, M. Hoelzl, C. Hopf, L. Horvath, T. Hoeschen, A. Houben, A. Hubbard, A. Huber, K. Hunger, V Igochine, M. Iliasova, T. Ilkei, K. Insulander Bjork, C. Ionita-Schrittwieser, I. Ivanova-Stanik, W. Jacob, N. Jaksic, F. Janky, A. Jansen van Vuuren, A. Jardin, F. Jaulmes, F. Jenko, T. Jensen, E. Joffrin, A. Kallenbach, S. Kalvin, M. Kantor, A. Kappatou, O. Kardaun, J. Karhunen, C-P Kasemann, S. Kasilov, A. Kendl, W. Kernbichler, E. Khilkevitch, A. Kirk, S. Kjer Hansen, V Klevarova, G. Kocsis, M. Koleva, M. Komm, M. Kong, A. Kraemer-Flecken, K. Krieger, A. Krivska, O. Kudlacek, T. Kurki-Suonio, B. Kurzan, B. Labit, K. Lackner, F. Laggner, A. Lahtinen, P. T. Lang, P. Lauber, N. Leuthold, L. Li, J. Likonen, O. Linder, B. Lipschultz, Y. Liu, A. Lohs, Z. Lu, T. Luda di Cortemiglia, N. C. Luhmann, T. Lunt, A. Lyssoivan, T. Maceina, J. Madsen, A. Magnanimo, H. Maier, J. Mailloux, R. Maingi, O. Maj, E. Maljaars, P. Manas, A. Mancini, A. Manhard, P. Mantica, M. Mantsinen, P. Manz, M. Maraschek, C. Marchetto, L. Marrelli, P. Martin, A. Martitsch, F. Matos, M. Mayer, M-L Mayoral, D. Mazon, P. J. McCarthy, R. McDermott, R. Merkel, A. Merle, D. Meshcheriakov, H. Meyer, D. Milanesio, P. Molina Cabrera, F. Monaco, M. Muraca, F. Nabais, V Naulin, R. Nazikian, R. D. Nem, A. Nemes-Czopf, G. Neu, R. Neu, A. H. Nielsen, S. K. Nielsen, T. Nishizawa, M. Nocente, J-M Noterdaeme, I Novikau, S. Nowak, M. Oberkofler, R. Ochoukov, J. Olsen, F. Orain, F. Palermo, O. Pan, G. Papp, I. Paradela Perez, A. Pau, G. Pautasso, C. Paz-Soldan, P. Petersson, P. Piovesan, C. Piron, U. Plank, B. Plaum, B. Plock, V Plyusnin, G. Pokol, E. Poli, L. Porte, T. Putterich, M. Ramisch, J. Rasmussen, G. Ratta, S. Ratynskaia, G. Raupp, D. Refy, M. Reich, F. Reimold, D. Reiser, M. Reisner, D. Reiter, T. Ribeiro, R. Riedl, J. Riesch, D. Rittich, J. F. Rivero Rodriguez, G. Rocchi, P. Rodriguez-Fernandez, M. Rodriguez-Ramos, V Rohde, G. Ronchi, A. Ross, M. Rott, M. Rubel, D. A. Ryan, F. Ryter, S. Saarelma, M. Salewski, A. Salmi, O. Samoylov, L. Sanchis Sanchez, J. Santos, O. Sauter, G. Schall, K. Schluter, K. Schmid, O. Schmitz, P. A. Schneider, R. Schrittwieser, M. Schubert, C. Schuster, T. Schwarz-Selinger, J. Schweinzer, E. Seliunin, A. Shabbir, A. Shalpegin, S. Sharapov, U. Sheikh, A. Shevelev, G. Sias, M. Siccinio, B. Sieglin, A. Sigalov, A. Silva, C. Silva, D. Silvagni, J. Simpson, S. Sipila, E. Smigelskis, A. Snicker, E. Solano, C. Sommariva, C. Sozzi, G. Spizzo, M. Spolaore, A. Stegmeir, M. Stejner, J. Stober, E. Strumberge, G. Suarez Lopez, H-J Sun, W. Suttrop, E. Sytova, T. Szepesi, B. Tal, T. Tala, G. Tardini, M. Tardocchi, D. Terranova, M. Teschke, E. Thoren, W. Tierens, D. Told, W. Treutterer, G. Trevisan, E. Trier, M. Tripsky, M. Usoltceva, M. Valisa, M. Valovic, M. van Zeeland, F. Vannini, B. Vanovac, P. Varela, S. Varoutis, N. Vianello, J. Vicente, G. Verdoolaege, T. Vierle, E. Viezzer, I Voitsekhovitch, U. von Toussaint, D. Wagner, X. Wang, M. Weiland, A. E. White, M. Willensdorfer, B. Wiringer, M. Wischmeier, R. Wolf, E. Wolfrum, Q. Yang, Q. Yu, R. Zagorski, I Zammuto, T. Zehetbauer, W. Zhang, W. Zholobenko, M. Zilker, A. Zito, H. Zohm, S. Zoletnik

Summary: This paper presents an overview of recent results obtained at the tokamak ASDEX Upgrade (AUG). Experimental and theoretical studies have been conducted to better understand various plasma phenomena such as plasma current redistribution, core transport, and power threshold of hydrogen plasmas. The focus has been on finding a fusion relevant integrated plasma scenario without large edge localized modes (ELMs), as well as establishing feedback control for the X-point radiator (XPR) position to achieve stable and detached ELM-free phases.

NUCLEAR FUSION (2022)

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Article Nuclear Science & Technology

Deuterium retention in tungsten fiber-reinforced tungsten composites

A. Kaercher, J. Riesch, P. Almanstoetter, A. Manhard, M. Balden, J. W. Coenen, K. Hunger, H. Maier, L. Raumann, D. Schwalenberg, R. Neu

Summary: In future fusion reactors, tungsten fiber-reinforced tungsten (W-f/W) composites have been developed to withstand unique conditions such as high temperatures, ion and neutron irradiation. These composites show higher deuterium retention compared to hot-rolled tungsten, indicating potential advantages in fusion environments.

NUCLEAR MATERIALS AND ENERGY (2021)

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Article Nuclear Science & Technology

Convolutional neural networks for the in-situ investigation of blistering on plasma-exposed metal surfaces

Alexander van Roessel, Udo von Toussaint, Armin Manhard

Summary: This article introduces a new framework for automatically analyzing bubble formation on metal surfaces using convolutional neural networks to address the limitations of existing methods. An effective automated bubble identification and tracking method is proposed for the formation of hydrogen-filled gas bubbles, and experimental results demonstrate the feasibility of the framework in identifying and tracking bubbles accurately.

NUCLEAR MATERIALS AND ENERGY (2021)

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Article Nuclear Science & Technology

Irradiation effects in tungsten-From surface effects to bulk mechanical properties

J. Riesch, A. Feichtmayer, J. W. Coenen, B. Curzadd, H. Gietl, T. Hoeschen, A. Manhard, T. Schwarz-Selinger, R. Neu

Summary: Advanced materials, such as tungsten fibre-reinforced composites, are used to address issues with baseline materials in fusion reactors. High-energy ions are used to simulate the effects of neutron irradiation on the mechanical properties of these materials. Fine tungsten wire provides a means to study irradiation damage and can be used to predict the properties of bulk composite materials.

NUCLEAR MATERIALS AND ENERGY (2022)

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Article Physics, Fluids & Plasmas

Investigation of ELM-related Larmor ion flux into toroidal gaps of divertor target plates

K. Krieger, M. Balden, M. Barac, I. Bogdanovic Radovic, D. Brida, M. Faitsch, J. P. Gunn, S. Markelj, M. Kelemen, A. Manhard, P. de Marne, R. A. Pitts, V. Rohde

Summary: A study on the International Tokamak Experimental Reactor (ITER) divertor has found that it may experience excessive heat loads due to edge localized modes (ELMs). These loads are caused by ELM ions expelled from the upstream region that arrive at the divertor without thermalization. The ions, due to their gyration around magnetic field lines, can penetrate gaps between target plates and deliver intense heat loads. Two experiments on the ASDEX Upgrade tokamak were conducted to confirm these findings, and they verified the predictions made by ion orbit simulations. The experiments also provided insights into the distribution of ion flux and the energy of ELM ions at the divertor.

NUCLEAR FUSION (2023)

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Article Nuclear Science & Technology

Visualizing spatially inhomogeneous hydrogen isotope diffusion by hydrogenography

A. Manhard, U. von Toussaint, P. Sand, M. Stienecker

Summary: Using a novel application of hydrogenography, we were able to directly observe the permeation behavior of deuterium in tungsten materials and discovered previously unknown phenomena. These findings are of great significance for accurately describing the diffusion behavior of hydrogen isotopes in fusion reactor materials.

NUCLEAR MATERIALS AND ENERGY (2023)

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Article Nuclear Science & Technology

Microstructural evolution of tungsten under thermal loads: A comparative study between cyclic high heat flux loading and isochronous furnace heating

Narguess Nemati, A. Manhard, H. Greuner, K. Hunger, B. Boeswirtha, E. Visca, J. H. You

Summary: Recrystallization is a significant microstructural change observed in tungsten under cyclic high heat flux (HHF) loads. The study compares the recrystallization behavior of tungsten samples heat-treated in a furnace versus those heated under cyclic HHF pulses. The results show that furnace heat-treatment may not properly simulate the recrystallization behavior observed under cyclic HHF loading conditions.

NUCLEAR MATERIALS AND ENERGY (2023)

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Article Materials Science, Multidisciplinary

H dissolution and desorption near He-V complexes in W surfaces with different orientations

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)

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Article Materials Science, Multidisciplinary

Effect of deposition parameters on characteristics and oxidation behavior of magnetron sputtered Cr coatings

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)

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Article Materials Science, Multidisciplinary

Automated analysis of grain morphology in TEM images using convolutional neural network with CHAC algorithm

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)

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Article Materials Science, Multidisciplinary

Model development for oxidation and degradation behavior of accident tolerant Cr coating on Zr alloy cladding under high temperature steam atmosphere

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)

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Article Materials Science, Multidisciplinary

Numerical and experimental development of cupronickel filler brazed joints for divertor and first wall components in DEMO fusion reactor

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)

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Article Materials Science, Multidisciplinary

Defect-specific strength factors and superposition model for predicting strengthening of ion irradiated Fe18Cr alloy

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)

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Article Materials Science, Multidisciplinary

Synthesis and characterization of sodium-aluminophosphate based glass-ceramics containing NZP phase for HLW immobilization

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)

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Article Materials Science, Multidisciplinary

High temperature oxidation of cold spray Cr-coated accident tolerant zirconium-alloy cladding with Nb diffusion barrier layer

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)

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Article Materials Science, Multidisciplinary

Irradiation creep measurement and microstructural analysis of chromium nitride-coated zirconium alloy using pressurized tubes

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)

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Article Materials Science, Multidisciplinary

Determination of impurity distribution in IG-11/110 nuclear graphite using TOF-SIMS

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)

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Article Materials Science, Multidisciplinary

Study of multi-pebble oxidation process in high-temperature gas-cooled reactor

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)

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Article Materials Science, Multidisciplinary

Synthesis and characterization of super occluded LiCl-KCl in zeolite-4A as a chloride salt waste form intermediate

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)

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Article Materials Science, Multidisciplinary

Hermeticity of SiC/SiC composite and monolithic SiC tubes irradiated under radial high-heat flux

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)

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Article Materials Science, Multidisciplinary

Theoretical estimation of multiple hydrogen isotope content in metal layers slowly co-deposited from plasmas

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)

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Article Materials Science, Multidisciplinary

Computational study of thermophysical properties of cerium doped UO2: Effect of oxidation states

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)

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