Article
Physics, Fluids & Plasmas
Anze Zaloznik, Matthew J. Baldwin, Russell P. Doerner, Gregory De Temmerman, Richard A. Pitts
Summary: This study improves the prediction capabilities of the De Temmerman scaling law by using new datasets and techniques, aiming to enhance the reliability of fusion fuel retention.
Article
Nuclear Science & Technology
M. J. Baldwin, A. Zaloznik, M. J. Simmonds, G. De Temmerman, R. P. Doerner
Summary: The formation of the sharp release feature in beryllium co-deposit thermal desorption studies is primarily influenced by low deposition temperature, higher D-2 pressure, and to a small degree, increased ion impact energy during deposition.
NUCLEAR MATERIALS AND ENERGY
(2021)
Article
Chemistry, Physical
Stjepko Fazinic, Georgios Provatas, Iva Bozicevic Mihalic, Tonci Tadic, Marek Rubel, Justyna Grzonka, Per Petersson, Anna Widdowson, Sunwoo Moon, Elzbieta Fortuna-Zalesna
Summary: Silicon plates were installed above the inner and outer divertor of the JET with the ITER-like wall (ILW) to monitor dust generation and deposition. The study found different categories of Be-rich particles, including co-deposits peeled off from plasma-facing components (PFC), complex multi-element spherical objects, and solid metal splashes and regular spherical droplets. Tungsten droplets were not detected, and the only W-containing particles were fragments of tungsten coatings from the divertor tiles.
Article
Nuclear Science & Technology
C. Ruset, E. Grigore, M. Mayer, F. Baiasu, C. Porosnicu, S. Krat, A. Widdowson, J. Likonen, M. Analytis, R. Meihsner, Jet Contributors
Summary: The JET divertor tiles were analyzed using GDOES technique, and it was found that the Be layer can protect the tile surface from erosion. Two mechanisms of D retention were identified based on the concentration of Be.
NUCLEAR MATERIALS AND ENERGY
(2022)
Article
Nuclear Science & Technology
C. Cupak, E. Pitthan, M. V. Moro, M. Fellinger, D. Primetzhofer, F. Aumayr
Summary: In this study, the retention of deuterium in beryllium was investigated using various analytical techniques. The results showed that approximately 85% of the retained deuterium was released during the primary desorption peak at 400 K, and a smaller secondary desorption peak was observed at 540 K. Interestingly, a beryllium oxide surface layer was present despite in-situ sputter-cleaning of the sample. Heating the sample to a temperature of 800 K completely removed all deuterium.
NUCLEAR MATERIALS AND ENERGY
(2022)
Article
Materials Science, Multidisciplinary
Paul Dinca, Cornel Staicu, Corneliu Porosnicu, Bogdan Butoi, Oana Gloria Pompilian, Ana Maria Banici, Flaviu Baiasu, Ion Burducea, Cristian P. Lungu
Summary: This study investigates the impact of Be-W mixed layers on the retention and release characteristics of hydrogen isotope D in thermonuclear fusion reactors. The morphology, crystallinity, and D release behavior of the mixed layers are discussed, showing that the retention of D is influenced by the trapping contribution of both Be and W. The presence of oxygen contamination in Be layers mitigates D retention in low energy trapping states and shifts the desorption chart towards a higher temperature.
Article
Physics, Fluids & Plasmas
P. Tsavalas, A. Lagoyannis, K. Mergia, M. Axiotis, S. Harissopulos, G. Provatas, S. Fazinic, T. Tadic, A. Widdowson, M. Rubel
Summary: This study analyzed castellated beryllium marker tiles from different locations in the JET tokamak and found that the amounts of carbon and deuterium deposition and retention on the castellation sides decrease with depth from the plasma-facing surface. There is no systematic difference between the deposition and retention on different castellation sides with respect to the ion/electron drift direction. The carbon and deuterium content is generally lower on the plasma-facing surface compared to the surfaces in the gaps of the castellation.
Article
Materials Science, Multidisciplinary
O. Ogorodnikova, D. Kovalenko, N. S. Klimov, K. Gutorov, A. Kaziev, M. M. Kharkov, V. S. Efimov, Yu M. Gasparyan, A. Poskakalov
Summary: In this study, tungsten samples were exposed to pulsed heat loads with deuterium and helium seeding in high-current plasma environment. It was found that the presence of helium reduces deuterium retention in tungsten, but this effect disappears when helium retention decreases below a certain threshold. Additionally, deuterium retention is higher at high temperatures compared to steady state plasma exposure.
JOURNAL OF NUCLEAR MATERIALS
(2022)
Article
Physics, Fluids & Plasmas
Yue Yuan, Ting Wang, Arkadi Kreter, Michael Reinhart, Alexis Terra, Soeren Moeeller, Long Cheng, Christian Linsmeier, Guang-Hong Lu
Summary: The effect of neon seeding on deuterium retention and surface modification of ITER-like forged tungsten was investigated in a plasma device. Neon seeding led to cracking and erosion of blister caps, reduction of small blisters, and increased total deuterium retention. The results suggest that neon seeding influences surface topography, deuterium diffusion and trapping, creating new deuterium-traps in the material.
Article
Physics, Fluids & Plasmas
S. Lee, Y. Hatano, S. Masuzaki, Y. Oya, M. Tokitani, M. Yajima, T. Otsuka, N. Ashikawa, Y. Torikai, N. Asakura, H. Nakamura, H. Kurotaki, T. Hayashi, T. Nozawa, A. M. Ito, J. Likonen, A. Widdowson, M. Rubel
Summary: In this study, the tritium retention in the castellated structure of beryllium limiters used in JET with the ITER-like wall was evaluated. Tritium was found to be deposited inside the grooves along with other elements. The tritium content was higher after the ILW1 campaign compared to the ILW3 campaign, which is attributed to a decrease in carbon impurities. The majority of tritium was retained in shallow regions in the grooves, and the retention patterns differed on plasma-facing surfaces.
Article
Nuclear Science & Technology
E. Pajuste, G. Kizane, L. Avotina, A. Vitins, A. S. Teimane
Summary: The ITER-Like Wall (ILW) project at Joint European Torus (JET) aims to test plasma-facing materials relevant to the ITER. Beryllium and tungsten tiles were used in different parts of the vacuum vessel, with tritium measurements showing varying concentrations across different positions and ILW campaigns. Tritium content was highest in samples from the outer wall of the vacuum vessel, particularly in the central part of tiles where plasma erosion had occurred.
NUCLEAR MATERIALS AND ENERGY
(2021)
Article
Nuclear Science & Technology
Sasa-Alexandra Yehia, Lavinia Gabriela Carpen, Flavian Stokker-Cheregi, Corneliu Porosnicu, Veronica Satulu, Cornel Staicu, Bogdan Butoi, Iulia Lungu, Francois Virot, Christian Grisolia, Gheorghe Dinescu
Summary: In this paper, a method to synthesize beryllium nanoparticles in a liquid medium using laser ablation is described. The key parameters affecting the size distribution were identified and analyzed using SEM, DLS, XPS, and TDS. The successful synthesis of beryllium dust and its surface morphology, particle size, chemical composition, and deuterium retention were investigated.
NUCLEAR MATERIALS AND ENERGY
(2022)
Article
Environmental Sciences
Jiawei Lu, Yongfu Li, Yanjiang Cai, Peikun Jiang, Bing Yu
Summary: In this study, a new type of slow-release fertilizer with high water retention, named HS-BCF, was fabricated by incorporating hydrotalcite and starch into traditional biochar-based compound fertilizers (BCF). The results showed that the incorporation of hydrotalcite and starch into BCF significantly increased the soil water-retention ratio and reduced the leaching of nutrients. Kinetic analysis revealed that the release of nutrients from HS-BCF was attributed to the coupling of the diffusion-controlled and relaxation-controlled mechanism. The pot experiments demonstrated that HS-BCF had higher N-P-K utilization efficiencies compared to BCF due to better synchronization between nutrient release and plant uptake.
Article
Nuclear Science & Technology
Kristof Kremer, Thomas Schwarz-Selinger, Wolfgang Jacob
Summary: In this study, the uptake of deuterium into tungsten through thin films of tungsten oxide was investigated. It was found that oxygen in the oxide film was partially removed by deuterium plasma, leading to tungsten enrichment near the surface. Deuterium accumulated in the oxide film but did not penetrate into the underlying self-damaged tungsten. After storage, deuterium content in the oxide layer decreased significantly, indicating that surface oxide films effectively block deuterium uptake into metallic tungsten.
NUCLEAR MATERIALS AND ENERGY
(2021)
Article
Materials Science, Multidisciplinary
Paul Dinca, Cornel Staicu, Corneliu Porosnicu, Oana G. Pompilian, Ana-Maria Banici, Bogdan Butoi, Cristian P. Lungu, Ion Burducea
Summary: Beryllium-deuterium co-deposited layers were obtained using DC magnetron sputtering technique with varying Ar/D-2 gas mixture compositions. Increasing deuterium content during deposition increased deuterium retention in beryllium layers up to 300%, primarily in low activation binding states. The layers release the majority of deuterium (above 99.99%) at temperatures lower than 700 K. The morphology of the layers is influenced by the substrate type and roughness.
Article
Physics, Fluids & Plasmas
M. Ben Yaala, D-F Scherrer, A. Saeedi, L. Moser, K. Soni, R. Steiner, G. De Temmerman, M. Oberkofler, L. Marot, E. Meyer
Article
Physics, Fluids & Plasmas
Y. Li, T. W. Morgan, J. A. W. Van Dommelen, S. Antusch, M. Rieth, J. P. M. Hoefnagels, D. Terentyev, G. De Temmerman, K. Verbeken, M. G. D. Geers
Article
Physics, Fluids & Plasmas
Trinayan Sarmah, Pubali Dihingia, Mizanur Rahman, J. Ghosh, P. Chaudhuri, Divesh N. Srivastava, B. Satpati, Sanjiv Kumar, M. Kakati, G. De Temmerman
Article
Physics, Fluids & Plasmas
Y. Li, T. W. Morgan, D. Terentyev, S. Ryelandt, A. Favache, S. Wang, M. Wirtz, J. P. M. Hoefnagels, J. A. W. van Dommelen, G. De Temmerman, K. Verbeken, M. G. D. Geers
Article
Physics, Fluids & Plasmas
Remi Delaporte-Mathurin, Etienne A. Hodille, Jonathan Mougenot, Yann Charles, Gregory De Temmerman, Floriane Leblond, Christian Grisolia
Summary: This study investigates the influence of hydrogen chemical potential continuity across solid material interfaces on gas particle flux and presents a method for rapid identification of material properties. It is found that the impact of chemical potential continuity on monoblock inventory only becomes significant after a long period of full power operation.
Article
Physics, Fluids & Plasmas
M. Rubel, Sunwoo Moon, P. Petersson, A. Widdowson, R. A. Pitts, S. Aleiferis, E. Fortuna-Zalesna, G. De Temmerman, R. Reichle
Summary: Mirror tests for ITER were conducted in JET for over 15 years, with a recent experiment during the third JET campaign showing no degradation in total reflectivity but an increase in diffuse reflectivity at shorter wavelengths. The mirrors were coated with a thin layer containing various elements, providing valuable input for ITER's erosion/deposition modeling and mirror cleaning methods consideration.
Article
Physics, Fluids & Plasmas
Y. Li, T. W. Morgan, T. Vermeij, J. W. M. Vernimmen, Th. Loewenhoff, J. P. M. Hoefnagels, J. A. W. van Dommelen, M. Wirtz, G. De Temmerman, K. Verbeken, M. G. D. Geers
Summary: The study found that under high-flux hydrogen plasma and high-cycle transient heat loads, recrystallization decreases the crack initiation heat flux factor threshold of tungsten and the cracks preferentially initiate at high angle grain boundaries.
Article
Physics, Fluids & Plasmas
T. W. Morgan, Y. Li, M. Balden, S. Brezinsek, G. De Temmerman
Summary: The study explores the impact of simulated ELM-like transient loading on the fatigue cracking threshold of tungsten under high-flux plasma and transient heat loading, revealing synergistic effects on surface morphology and damage extent. A significant reduction in fatigue cracking threshold was found for base temperatures above 1150 degrees C, with cracked surfaces becoming over ten times rougher than the original microstructure. Additionally, seeding impurities can significantly increase surface roughness compared to pure H plasma roughening.
Article
Physics, Fluids & Plasmas
Y. Li, T. W. Morgan, J. van den Berg-Stolp, J. W. Genuit, G. De Temmerman, J. P. M. Hoefnagels, J. A. W. van Dommelen, K. Verbeken, M. G. D. Geers
Summary: The study reveals that the heat loads induced by ELM-like hydrogen plasma on tungsten in future fusion devices are affected by the interaction between recycling neutrals and plasma ions. Through a series of experiments, observations of plasma stagnation and cooling during pulses were made, indicating the impact of plasma-neutral interaction on power deposition behavior.
PLASMA PHYSICS AND CONTROLLED FUSION
(2021)
Article
Nuclear Science & Technology
Gregory De Temmerman, Kalle Heinola, Dmitriy Borodin, Sebastijan Brezinsek, Russell P. Doerner, Marek Rubel, Elzbieta Fortuna-Zalesna, Christian Linsmeier, Daisuke Nishijima, Kai Nordlund, Michael Probst, Juri Romazanov, Elnaz Safi, Thomas Schwarz-Selinger, Anna Widdowson, Bastiaan J. Braams, Hyun-Kyung Chung, Christian Hill
Summary: This paper comprehensively investigates the behavior of beryllium under fusion-relevant conditions, covering erosion mechanisms, migration, fuel retention, and dust generation. By combining laboratory studies, computer simulations, and experimental experiences, it aims to provide a rich dataset for ITER while identifying gaps in research that need to be addressed.
NUCLEAR MATERIALS AND ENERGY
(2021)
Article
Physics, Fluids & Plasmas
Anze Zaloznik, Matthew J. Baldwin, Russell P. Doerner, Gregory De Temmerman, Richard A. Pitts
Summary: This study improves the prediction capabilities of the De Temmerman scaling law by using new datasets and techniques, aiming to enhance the reliability of fusion fuel retention.
Article
Physics, Fluids & Plasmas
Remi Delaporte-Mathurin, Hao Yang, Julien Denis, James Dark, Etienne A. Hodille, Gregory De Temmerman, Xavier Bonnin, Jonathan Mougenot, Yann Charles, Hugo Bufferand, Guido Ciraolo, Christian Grisolia
Summary: Increasing the fueling rate increases retention in the private zone and slightly decreases retention at the strike points; increasing the input power increases inventory at the strike points and has little effect on inventory in the private flux region; the inventory in the ITER divertor is not strongly dependent on the divertor neutral pressure.
Article
Physics, Multidisciplinary
Miroslaw Zlobinski, G. De Temmerman, C. Porosnicu, D. Matveev, B. Unterberg, G. Sergienko, S. Brezinsek, D. Nicolai, A. Terra, M. Rasinski, B. Spilker, M. Freisinger, S. Moeller, Ch Linsmeier, C. P. Lungu, P. Dinca
Article
Physics, Multidisciplinary
D. Matveev, M. Zlobinski, G. De Temmerman, B. Unterberg, C. Linsmeier
Article
Physics, Multidisciplinary
T. W. Morgan, M. Balden, T. Schwarz-Selinger, Y. Li, T. H. Loewenhoff, M. Wirtz, S. Brezinsek, G. De Temmerman
