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
Nuclear Science & Technology
Wei Zhao, Yuzhong Jin, Lin Nie, Longwen Yan, Chunjia Liu, Fan Feng, Youyu Lian, Hongxia Zhou, Guangwu Zhong, Christopher Watts
Summary: This article introduces a new design of ITER divertor Langmuir probe (DLP), called full-tungsten design. By using tungsten as the heat shield material instead of the previous copper brazing layer, the poor thermal fatigue issue of the copper brazing layer in the previous design is addressed. The analysis shows good thermal and mechanical behavior after structural optimization, and the feasibility of the design and manufacturing technology is demonstrated through the R & D work of prototypes.
FUSION ENGINEERING AND DESIGN
(2022)
Article
Nuclear Science & Technology
Nasr Ghoniem, Sohun Patel, Arian Ghazari, Warren Nadvornick, Dylan Dickstein, Brian Williams, Don Hughes
Summary: We conducted a comprehensive study on a new modular finger component with a hexagonal tungsten foam armor tile bonded to the top surface of the water-cooled finger unit. The mechanical, thermal, and particle transport properties of the tungsten foam armor were determined and used for simulations. The optimized design was fabricated and tested under various thermal loading conditions, showing successful cooling of fusion device walls.
FUSION ENGINEERING AND DESIGN
(2023)
Article
Nuclear Science & Technology
G. Pintsuk, M. Missirlian, G-N Luo, Q. Li, W. Wang, D. Guilhem, J. Bucalossi
Summary: The qualification of suppliers for actively cooled tungsten targets for the lower divertor of WEST involved cyclic high heat flux tests on small-scale mock-ups based on ITER design, resulting in successful performance and subsequent qualification through hardness tests and microstructural analyses.
FUSION ENGINEERING AND DESIGN
(2021)
Article
Nuclear Science & Technology
R. Neu, H. Maier, B. Boeswirth, S. Elgeti, H. Greuner, K. Hunger, J. Kondas, A. von Mueller
Summary: Cold gas spraying was investigated for the production of thick tungsten coatings for use in fusion devices. A systematic study using tungsten and tantalum powder mixtures was performed due to the brittle nature of tungsten. Coatings with negligible porosity and good adhesion were achieved using a 90 vol% tungsten mixture, resulting in a 70 vol% tungsten content in the coating. High heat flux experiments showed good performance under low steady-state loads, but cracks appeared during high power transients.
NUCLEAR MATERIALS AND ENERGY
(2023)
Article
Nuclear Science & Technology
Yann Corre, Torsten Loewenhoff, Marianne Richou, Sebastijan Brezinsek, Jan Coenen, Renaud Dejarnac, Mathilde Diez, Nicolas Fedorczak, Mehdi Firdaouss, Jonathan Gaspar, Alex Grosjean, James-Paul Gunn, Thierry Loarer, Celine Martin, Gerald Pintsuk, Pierre Reilhac, Quentin Tichit, Emmanuelle Tsitrone, West Team
Summary: The consequences of tungsten (W) cracking on divertor lifetime and plasma operation are high priority issues for ITER. In order to assess the damage evolution after tokamak plasma exposure, one actively cooled plasma facing unit (PFU) has been pre-damaged in a High Heat Flux (HHF) facility before its installation in WEST. The plasma exposure and dedicated experiment on the damaged PFU revealed significant broadening and new cracks in the electron beam loaded area.
NUCLEAR MATERIALS AND ENERGY
(2023)
Article
Nuclear Science & Technology
Y. Anquetin, J. Gaspar, Y. Corre, Q. Tichit, J. L. Gardarein, G. Laffont, M. Missirlian, C. Pocheau, West Team
Summary: The WEST project aims to study the behavior and durability of the ITER-like divertor monobloc components under relevant heat loads. The lower divertor in phase 2 of WEST is equipped with actively cooled tungsten Plasma Facing Units (PFU) that can withstand 10MW/m2 in steady state. New diagnostics, including thermocouples and fiber Bragg gratings, are used to measure the heat loading in the divertor and estimate the surface heat flux using an inverse method. The performance of each diagnostic is evaluated using synthetic measurements and it is shown that they can accurately estimate the spatial distribution of heat fluxes in WEST.
FUSION ENGINEERING AND DESIGN
(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
M. Fukuda, Y. Seki, K. Ezato, K. Yokoyama, H. Nishi, S. Suzuki, T. Hirai
Summary: This study investigated the variation in material properties and impurity levels of tungsten monoblocks manufactured using plates supplied by two Japanese companies, concluding that the variations were acceptable for use in the full-scale plasma-facing unit prototype. This provides a foundation for the final validation of the material and OVT manufacturing technology.
FUSION ENGINEERING AND DESIGN
(2021)
Article
Nuclear Science & Technology
N. Chanet, Y. Corre, R. Cotillard, J. Gaspar, G. Laffont, C. Pocheau, G. Caulier, C. Dechelle, B. De Gentile, C. Destouches, L. Dubus, F. Gallay, C. Hernandez, M. Missirlian, M. Richou, N. Roussel, B. Santraine
Summary: This study focuses on temperature measurement in plasma-facing components using femtosecond FBG technology, aiming to improve measurement accuracy and range in high-temperature environments. By utilizing more advanced techniques, the research successfully addresses measurement issues at elevated temperatures.
FUSION ENGINEERING AND DESIGN
(2021)
Article
Nuclear Science & Technology
Yan Huang, Jizhong Sun, Rui Ding, Chaofeng Sang, Dezhen Wang
Summary: This paper uses a two-dimensional conduction model to analyze the thermal performance of ITER W/Cu monoblock under ITER-like conditions. The model considers various heat conduction processes and employs coupling cooling water condition. The simulation results show that cooling water conditions play a significant role in the thermal performance of W/Cu monoblock, especially for Cu heat sink materials during steady state. The paper also presents analysis based on typical VDE heat loads.
FUSION ENGINEERING AND DESIGN
(2023)
Article
Nuclear Science & Technology
Kuo Zhang, Jeong-Ha You
Summary: Within the EUROfusion framework, the thermal stress and fracture analysis of the DEMO-divertor design with a copper alloy heat sink were carried out to evaluate the structural integrity of the tungsten armor of the plasma facing component. Finite element method (FEM) and extended finite element method (XFEM) were used to assess the influence of mesh and tungsten plasticity, fracture strength, and toughness on crack initiation and propagation.
FUSION ENGINEERING AND DESIGN
(2022)
Article
Physics, Fluids & Plasmas
Xueyun Wang, Xueqiao Xu, Philip B. Snyder, Zeyu Li
Summary: The BOUT++ six-field turbulence code was used to simulate different scenarios of ITER operation and compare their characteristics. The study found that different types of ELMs dominate in different scenarios and result in varying energy loss fractions.
Article
Nuclear Science & Technology
E. Kaveeva, S. Makarov, I. Senichenkov, V. Rozhansky, I. Veselova, X. Bonnin, R. A. Pitts
Summary: The impact of the ionization source in the ITER far SOL on the overall SOL performance has been numerically studied using SOLPS-ITER modeling. It has been found that this source can significantly affect the retention of the seeded impurity radiator (Ne) in the divertor and the plasma temperature in the far SOL. Both factors indicate the beneficial effect of high fuel throughput on separatrix and pedestal plasma composition.
NUCLEAR MATERIALS AND ENERGY
(2023)
Review
Materials Science, Multidisciplinary
J. H. You, E. Visca, T. Barrett, B. Boeswirth, F. Crescenzi, F. Domptail, G. Dose, M. Fursdon, F. Gallay, H. Greuner, K. Hunger, A. Lukenskas, A. V. Mueller, M. Richou, S. Roccella, C. Vorpahl, K. Zhang
Summary: The divertor target is a critical component in a fusion power plant responsible for particle and power exhaust. Recent R&D efforts have led to the successful development and evaluation of various high-heat-flux (HHF) technologies for divertor targets. Results from HHF testing show that all design variants performed well, with two designs remaining intact even under higher heat flux densities.
JOURNAL OF NUCLEAR MATERIALS
(2021)
