Zobrazeno 1 - 10
of 764
pro vyhledávání: '"Plasma-wall Interaction"'
Autor:
H. Bufferand, G. Ciraolo, R. Düll, G. Falchetto, N. Fedorczak, Y. Marandet, V. Quadri, M. Raghunathan, N. Rivals, F. Schwander, E. Serre, S. Sureshkumar, P. Tamain, N. Varadarajan
Publikováno v:
Nuclear Materials and Energy, Vol 41, Iss , Pp 101824- (2024)
First principle modelling of edge plasma turbulence including neutrals and plasma recycling on the wall remains a challenge, in particular due to the long time scales necessary to simulate to reach particle balance. In this contribution, we propose a
Externí odkaz:
https://doaj.org/article/af4a47461ece4cef88891bd5d5e5aef7
Autor:
A. Kirschner, S.S. Henderson, S. Brezinsek, J. Romazanov, C. Baumann, M. Kovari, Ch. Linsmeier
Publikováno v:
Nuclear Materials and Energy, Vol 41, Iss , Pp 101827- (2024)
Net tungsten erosion and deposition profiles are simulated for the outer and inner lower divertor of STEP, a spherical prototype fusion reactor targeting ∼ 2040. In this contribution, previous modelling work [1] has been extended by studying the in
Externí odkaz:
https://doaj.org/article/8a2cf2eeee84435497d6af4bad78d7bf
Autor:
N. Varadarajan, H. Bufferand, G. Ciraolo, L. Cappelli, P. Tamain, N. Rivals, S. Sureshkumar, V. Quadri, L. de Gianni
Publikováno v:
Nuclear Materials and Energy, Vol 41, Iss , Pp 101818- (2024)
The W impurity species was introduced in the multi-component edge fluid code SOLEDGE3X, in its 2D transport version. To do so, several physical ingredients have been implemented. Firstly, W gross erosion is calculated using the Garcia-Rosales formula
Externí odkaz:
https://doaj.org/article/cde4336e5c6e4c60892ee9c7fabe141f
Publikováno v:
Nuclear Materials and Energy, Vol 42, Iss , Pp 101836- (2025)
The neutralization of an ion particle on a surface is a key issue in plasma–wall interactions. We investigated helium ion injection onto a tungsten surface using time-dependent density functional theory (TDDFT) simulations. We developed the TDDFT c
Externí odkaz:
https://doaj.org/article/a9657f5754c141b5a58eebbd642b7534
Autor:
Sanath J. Shetty, Matej Veis, Sahithya Atikukke, Petr Bartoň, Martin Jeřáb, Renaud Dejarnac, Pavel Veis
Publikováno v:
Nuclear Materials and Energy, Vol 37, Iss , Pp 101547- (2023)
Plasma-facing materials in tokamak nuclear reactors are subject to intense heat and radiation. The design of liquid metal (LM) divertor walls has several advantages over the solid counterparts. It is important to understand the migration and re-depos
Externí odkaz:
https://doaj.org/article/cf6c415d67664fe9852d4b366f260f30
Autor:
Guo-jian Niu, Gakushi Kawamura, Shu-yu Dai, Zhong-shi Yang, Fang Ding, Qian Xu, Rong Wang, Tao He, Guang-Nan Luo
Publikováno v:
Nuclear Fusion, Vol 64, Iss 2, p 026009 (2024)
Material sputtering and erosion are key issue in fusion science. In the steady state, tungsten sputtering can be maintained at a low level. However, tungsten is seriously sputtered by the hot plasma from edge localized mode (ELM) bursts. The time evo
Externí odkaz:
https://doaj.org/article/845cf275bb694685b143a256ead686af
Autor:
Yann Munschy, Emily Bourne, Guilhem Dif-Pradalier, Peter Donnel, Philippe Ghendrih, Virginie Grandgirard, Yanick Sarazin
Publikováno v:
Nuclear Fusion, Vol 64, Iss 4, p 046013 (2024)
The interaction between a plasma and a solid surface is studied in a (1D–1V) kinetic framework using a localized particle and convective energy source. Matching the quasineutral plasma region and sheath horizon is addressed in the fluid framework w
Externí odkaz:
https://doaj.org/article/77bc85108dd94043b882b65b0fedecb4
Autor:
Yann Munschy, Emily Bourne, Guilhem Dif-Pradalier, Peter Donnel, Philippe Ghendrih, Virginie Grandgirard, Yanick Sarazin
Publikováno v:
Nuclear Fusion, Vol 64, Iss 5, p 056027 (2024)
The interaction between a plasma and a solid surface is studied in a (1D-1V) kinetic approach using immersed boundary conditions and penalization to model the wall. Two solutions for the penalized wall region are investigated that either allow curren
Externí odkaz:
https://doaj.org/article/5ff79a940e6e4dc886c1bf2f25e44524
Autor:
K.A. Jadeja, J. Ghosh, K.M. Patel, A.B. Patel, R.L. Tanna, Kiran Patel, B.G. Arambhadiya, K.D. Galodiya, Rohit Kumar, S. Aich, Harshita Raj, L. Pradhan, M.B. Chowdhuri, R. Manchanda, N. Ramaiya, Nandini Yadava, Sharvil Patel, Kajal Shah, Dipexa Modi, A. Gauttam, K. Singh, S. Dolui, Ankit Kumar, B. Hegde, A. Kumawat, Minsha Shah, R. Rajpal, U. Nagora, P.K. Atrey, S.K. Pathak, Shishir Purohit, A. Adhiya, Manoj Kumar, Kumudni Assudani, D. Kumavat, S.K. Jha, K.S. Shah, M.N. Makwana, Shivam Gupta, Supriya Nair, Kishore Mishra, D. Raju, P.K. Chattopadhyay, B.R. Kataria
Publikováno v:
Nuclear Fusion, Vol 64, Iss 10, p 106048 (2024)
Effective control of impurities and precise regulation of the fueling gas are supreme prerequisites for optimal operation in any fusion device. Conventional wall-conditioning methods fall short of achieving optimal wall conditioning. Conventional wal
Externí odkaz:
https://doaj.org/article/06d53f57a8074693b2f3497191a371a2
Autor:
M. Richou, Y. Corre, M. Diez, A. Durif, C. Guillemaut, P. Reilhac, Q. Tichit, E. Tsitrone, D. Dorow-Gerspach, Th. Loewenhoff, M. Wirtz, A. Grosjean, C. Martin, G. Giacometti, A. Aretz, M. Spahn, J. Gaspar, the WEST Team
Publikováno v:
Nuclear Fusion, Vol 64, Iss 10, p 106002 (2024)
The evaluation of the impact of plasma-facing units (PFUs) damage on subsequent plasma operation is an important issue for ITER. This is one of the topic addressed by the operation of dedicated PFUs in WEST. From the start of WEST in 2017, few ITER g
Externí odkaz:
https://doaj.org/article/697a44577b37400dacf9e46bb469c276