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621
A Comprehensive Examination of Bandgap Semiconductor Switches
Published 2021-01-01Get full text
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622
Cleanroom assembly of the IFMIF SRF Linac
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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623
SOSYAL SINIFLARDA TÜKETİMİN SINIF BELİRLEYİCİLİK ROLÜ
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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624
Negative Ion Beam Emittance Calculations
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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625
Tritium Breeding Performance Analysis of HCLL Blanket Fusion Reactor Employing Vanadium Alloy (V-5Cr-5Ti) as First Wall Material
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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626
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627
A Traffic Management System by Identifying Pollution Hotspots Among Sensitive Points in a Smart City
Published 2025-01-01Get full text
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628
Thermal and structural effects of amino acids on the interactions of thiamine hydrochloride with water
Published 2025-03-01Get full text
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629
Transport and profile broadening in the private flux region of ASDEX upgrade and role for power exhaust
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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630
Modelling the brittle failure of graphite induced by the controlled impact of runaway electrons in DIII-D
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631
Heat and Helium-3 Fluxes from Teide Volcano, Canary Islands, Spain
Published 2019-01-01Get full text
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632
A (DES)HUMANIDADE DO PROCEDIMENTO DE PERÍCIA MÉDICA NO BENEFÍCIO POR INCAPACIDADE: LÓGICA IMUNITÁRIA QUE REQUER REFLEXIVIDADE FRATERNA
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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633
Enhanced pedestal transport driven by edge collisionality on Alcator C-Mod and its role in regulating H-mode pedestal gradients
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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634
The scoping, design, and plasma physics optimization of the Eos neutron source stellarator
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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635
A novel TID + IDN controller tuned with coatis optimization algorithm under deregulated hybrid power system
Published 2025-02-01Get full text
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636
Experimental study and gyrokinetic simulations of isotope effects on core heat transport in JET tokamak deuterium and tritium plasmas
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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637
Research on ion cyclotron emission driven by deuterium–deuterium fusion-produced tritium ions on the Experimental Advanced Superconducting Tokamak
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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638
Implementing deep learning-based disruption prediction in a drifting data environment of new tokamak: HL-3
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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639
Comparison of plasma start-up with high Z and low Z first wall in WEST
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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640
Accelerating discoveries at DIII-D with the Integrated Research Infrastructure
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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