Showing 621 - 640 results of 3,044 for search '"ITER"', query time: 0.10s Refine Results
  1. 621
  2. 622

    Cleanroom assembly of the IFMIF SRF Linac by Chambrillon Janic Kevin, Bazin Nicolas, Carin Yann, Duglué Daniel, Dzitko Hervé, Ebisawa Takashi, Gex Dominique, Jimenez-Rey David, Hasegawa Kazuo, Kondo Keitaro, Kumagai Kohki, Masuda Kai, Molla Joaquin, Phillips Guy, Scantamburlo Francesco

    Published 2024-01-01
    “…In complement to the development activities for fusion reactors (JT-60SA & ITER), Fusion for Energy contributes to the R&D for material characterisation facilities. …”
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  3. 623

    SOSYAL SINIFLARDA TÜKETİMİN SINIF BELİRLEYİCİLİK ROLÜ by Sezgin Açıkalın, Ekrem Gül

    Published 2006-12-01
    “…Sosyal sınıflar arasında oluşan ayrışma ve çekişme zemini bireyleri yaptıkları tüketimlerde bazen üst sınıftanmış bazen de o sınıftan değilmiş izlenimini vermeye iter. İnsanlar sosyal sınıflardaki yerlerine göre tüketim kararlarını değiştirebilir ve ait olmak istediği statüyü işaret edecek şekilde bu kararları alabilirler.…”
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  4. 624

    Negative Ion Beam Emittance Calculations by M. Turek, P. Węgierek

    Published 2020-03-01
    “…Computer simulations are commonly used to support design and optimisation of powerful negative ion sources for the needs of future thermonuclear reactors like e. g. ITER. The aim of the paper was to study changes of produced beam quality (described by its emittance and brightness) with the geometry of the extraction system as well as extraction voltage.A two-dimensional Particle-in-Cell (PIC) method based code was applied to model Hions and electrons extraction from the ion source plasma chamber through the opening with bevelled surface. …”
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  5. 625

    Tritium Breeding Performance Analysis of HCLL Blanket Fusion Reactor Employing Vanadium Alloy (V-5Cr-5Ti) as First Wall Material by Indah Rosidah Maemunah, Zaki Su’ud, Abdul Waris, Dwi Irwanto

    Published 2022-01-01
    “…Neutronic analysis in the HCLL blanket module has been established, and the calculation was performed by the ITER team, including the first wall (FW). In this study, seven materials have been investigated for FW material by considering characteristics such as high neutron fluence capability, low degradation, under irradiation, and high compatibility for blanket material. …”
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  6. 626
  7. 627
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  9. 629

    Transport and profile broadening in the private flux region of ASDEX upgrade and role for power exhaust by D. Brida, G. Grenfell, O. Grover, D. Silvagni, M. Faitsch, U. Stroth, the ASDEX Upgrade Team, the EUROfusion Tokamak Exploitation Team

    Published 2025-01-01
    “…According to the model, the ion PFR width increases with the distance Δ R between the outer target and X-point major radii, and scales inversely with the poloidal magnetic field $B_\mathrm p$ . For the tokamaks ITER and SPARC the model predicts PFR widths below 0.3 mm.…”
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  10. 630
  11. 631
  12. 632

    A (DES)HUMANIDADE DO PROCEDIMENTO DE PERÍCIA MÉDICA NO BENEFÍCIO POR INCAPACIDADE: LÓGICA IMUNITÁRIA QUE REQUER REFLEXIVIDADE FRATERNA by Claudine Costa Smolenaars, Daniela Regina Pellin, Sandra Regina Martini

    Published 2024-09-01
    “…Como promover um raciocínio ecológico na proteção de direitos sociais da saúde e da previdência, de modo a reduzir o iter processual ao benefício e reduzir a vulnerabilidade social, bem como os conflitos? …”
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  13. 633

    Enhanced pedestal transport driven by edge collisionality on Alcator C-Mod and its role in regulating H-mode pedestal gradients by M.A. Miller, J.W. Hughes, A.M. Rosenthal, S. Mordijck, R. Reksoatmodjo, M. Wigram, J. Dunsmore, F. Sciortino, R.S. Wilcox, T. Odstrčil

    Published 2025-01-01
    “…The transition is well correlated with the experimentally observed value of $P_\mathrm{net}^\mathrm{crit}$ . SOLPS-ITER modeling is performed for select discharges from the power scan, constrained with experimental electron and neutral densities, measured at the outer midplane. …”
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  14. 634

    The scoping, design, and plasma physics optimization of the Eos neutron source stellarator by C.P.S. Swanson, D.A. Gates, S.T.A. Kumar, M.F. Martin, T.G. Kruger, D.W. Dudt, P.J. Bonofiglo, the Thea Energy team

    Published 2025-01-01
    “…A potentially advantageous regime is described in which modern precisely-quasisymmetric stellarators, new high-temperature superconductors, ITER-derived neutral beam injection, and new high-frequency gyrotrons enable a suitible target plasma with hot electrons, cold ions, peaked density and temperature profiles, and high beam-injected ion density. …”
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  15. 635
  16. 636

    Experimental study and gyrokinetic simulations of isotope effects on core heat transport in JET tokamak deuterium and tritium plasmas by D. Brioschi, P. Mantica, A. Mariani, N. Bonanomi, E. Delabie, J. Garcia, N. Hawkes, I. Jepu, D. Keeling, E. Lerche, E. Litherland-Smith, C.F. Maggi, S. Menmuir, G. Szepesi, D. Taylor, D. Van Eester, JET Contributors

    Published 2025-01-01
    “…This paper presents a study on the dependence of the ion temperature stiffness on the plasma main ion isotope mass in JET ITER-like wall and C wall discharges. To this aim, a database of H, D and T shots is analyzed, including new dedicated shots, comparing experiments with lower and higher power injected by the NBI system. …”
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  17. 637

    Research on ion cyclotron emission driven by deuterium–deuterium fusion-produced tritium ions on the Experimental Advanced Superconducting Tokamak by Huapeng Zhang, Lunan Liu, Wei Zhang, Xuan Sun, Xinjun Zhang, Zhengshuyan Wang, Zelin Xu, Jiadong Zhang, Weijian Qin, Liuxin Li, Yuhao Jiang, Sichun Qiu, Chengming Qin, Guanghui Zhu, Yongxin Zhu, Kai Zhang, Tao Jin, Zhiping Li

    Published 2025-01-01
    “…It is important to study ICE because ICE can help distinguish the species of fusion-product ions, which can also help monitor the fusion alpha ions in large fusion devices, such as CFETR, DEMO, and ITER.…”
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  18. 638

    Implementing deep learning-based disruption prediction in a drifting data environment of new tokamak: HL-3 by Zongyu Yang, Wulyu Zhong, Fan Xia, Zhe Gao, Xiaobo Zhu, Jiyuan Li, Liwen Hu, Zhaohe Xu, Da Li, Guohui Zheng, Yihang Chen, Junzhao Zhang, Bo Li, Xiaolong Zhang, Yiren Zhu, Ruihai Tong, Yunbo Dong, Yipo Zhang, Boda Yuan, Xin Yu, Zongyuhui He, Wenjing Tian, Xinwen Gong, Min Xu

    Published 2025-01-01
    “…This problem is often overlooked in previous implementations on steadily operating tokamaks, necessitating greater attention in future tokamaks like ITER. To address these challenges, innovative modules including predict-first neural network, data augmentation, and pseudo data placeholders are developed and implemented, which promotes the accuracy by up to 20%. …”
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  19. 639

    Comparison of plasma start-up with high Z and low Z first wall in WEST by C. Guillemaut, K. Afonin, G. Bodner, J. Bucalossi, Y. Corre, P. Devynck, A. Diallo, M. Diez, N. Fedorczak, A. Gallo, B. Guillermin, V. Lapleigne, R. Lunsford, P. Maget, J. Morales, Ph. Moreau, the WEST Team, the EUROfusion Tokamak Exploitation Team

    Published 2025-01-01
    “…The choice of first wall material is of paramount importance for the plasma start-up conditions in ITER and future fusion power plants. In this context, the present work focuses on the correlations between first wall impurity sources and total radiated power during plasma start-up in the tungsten (W) Environment in Steady-state Tokamak (WEST). …”
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  20. 640

    Accelerating discoveries at DIII-D with the Integrated Research Infrastructure by T. Bechtel Amara, S. P. Smith, Z. A. Xing, S. S. Denk, A. Deshpande, A. O. Nelson, C. Simpson, E. W. DeShazer, T. F. Neiser, O. Antepara, C. M. Clark, J. Lestz, J. Colmenares, N. Tyler, P. Ding, M. Kostuk, E. D. Dart, R. Nazikian, T. Osborne, S. Williams, T. Uram, D. Schissel

    Published 2025-01-01
    “…The workflows developed for this project are intended to serve as prototypes that can be replicated on other experiments and can be run to provide timely and essential information for ITER, as well as next stage fusion power plants.…”
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