核能 · 全部实体（第 20 / 100 页）

本页收录第 1901–2000 条，共 10000 条 · 返回 核能 首页

• Retraction Note: Measurement of Plasma Poloidal Beta in Presence of Resonant Helical Field in IR-T1 Tokamak
  crossref Ahmad Salar Elahi, Mahmood Ghoranneviss 2024-08-03T00:01:50Z 置信度 0.70
• Determination of Tokamak Plasma Electrical Fluctuations using the Langmuir Probe [Withdrawn]
  crossref K. Ghanbari, A. S. Elahi, M. Ghorannevis 2016-07-07T20:15:29Z 置信度 0.70
• Parameter Space Constraints for Compact Spherical Tokamak Fusion Reactors
  crossref P. N. Maya, S. P. Deshpande 2023-10-09T16:02:37Z 置信度 0.70
• Retraction Note: Investigation of Effects of Toroidal Field Ripple on Plasma Poloidal Beta in IR-T1 Tokamak
  crossref A. Salar Elahi, M. Ghoranneviss 2024-07-07T23:13:03Z 置信度 0.70
• Retraction Note: Biasing Effect on the Edge Plasma Electrical Fluctuations in IR-T1 Tokamak
  crossref K. Mikaili Agah, A. Salar Elahi, M. Ghoranneviss 2024-07-04T09:01:39Z 置信度 0.70
• Аналитические модели для вычисления инкремента неустойчивости вертикального положения плазмы токамака.
  crossref N.V. Chukashev, V.D. Pustovitov 2024-09-04T19:44:32Z 置信度 0.70
• Retraction Note to: Turbulent Transport in the Tokamak Edge Plasma and SOL Region
  crossref S. Meshkani, M. Ghoranneviss, M. Lafouti, A. Salar Elahi 2024-07-04T11:02:33Z 置信度 0.70
• Tokamak to stellarator conversion using permanent magnets
  Abstract With the advances in the optimization of magnetic field equilibria, stellarators have become a serious alternative to the tokamak, bringing this concept to the forefront of the pursuit of fusion energy. In order to be successful in experimentally demo…
  crossref M Madeira, R Jorge 2024-06-07T22:27:16Z 置信度 0.70
• PCC-Trans: a time series feature selection and model framework for tokamak discharge process in EAST
  crossref Binqian Cheng, Chenguang Wan, Xiaojuan Liu, Zhi Yu 等 2024-06-13T22:20:00Z 置信度 0.70
• Multiple Cell Array Detector for a Heavy Ion Beam Probe on the T-15MD Tokamak
  crossref E. A. Vinitskiy, O. D. Krohalev, L. G. Eliseev, A. V. Melnikov 2025-02-01T16:52:38Z 置信度 0.70
• Simulation  of Neutral Beam Injection Towards Fast Ion Study in Thailand Tokamak-1
  crossref Apiwat Wisitsorasak, Kunihiro Ogawa, Siriyaporn Sangaroon, Boonyarit Chatthong 等 2024-12-28T22:36:51Z 置信度 0.70
• Retraction Note: Plasma Confinement Modification in IR-T1 Tokamak by Velocity Shear Stabilization
  crossref M. Ghoranneviss, M. Lafouti, S. Meshkani, A. Salar Elahi 2024-07-09T02:01:50Z 置信度 0.70
• Tokamak divertor plasma emulation with machine learning
  Abstract Future tokamak devices that aim to create conditions relevant to power plant operations must consider strategies for mitigating damage to plasma facing components in the divertor. One of the goals of MAST-U tokamak operations is to inform these consid…
  crossref G.K. Holt, A. Keats, S. Pamela, M. Kryjak 等 2024-05-23T22:23:23Z 置信度 0.70
• Simulations of tokamak edge plasma turbulent fluctuations based on a minimal 3D model
  Abstract A new simulation model for tokamak boundary plasma, SOLT3D, is implemented in the BOUT++ framework (Dudson et al 2009 Comput. Phys. Commun. 180 1467). The simulation model includes a set of dynamic equations describing collisional boundary plasma and …
  crossref M V Umansky, B I Cohen, I Joseph 2024-02-21T17:27:18Z 置信度 0.70
• Hard X-Ray Collimation System at the T-15MD Tokamak
  crossref V. I. Tepikin, P. V. Savrukhin, E. A. Shestakov, P. D. Lisovoi 等 2024-11-05T06:03:22Z 置信度 0.70
• Retraction Note to: A Novel Optical Technique Based on Image Processing for Determination of Tokamak Plasma Displacement
  crossref Ahmad Salar Elahi, Mahmood Ghoranneviss 2024-07-04T09:01:39Z 置信度 0.70
• C-HIL Implementation of Cascaded Multilevel Inverter for Vertical Stabilization and Radial Control Power Supplies of Divertor Tokamak Test
  crossref Giovanni Griva, Salvatore Musumeci, Fausto Stella, Radu Bojoi 等 2024-10-04T17:31:44Z 置信度 0.70
• Control System for Dispersion Interferometer on Globus-M2 Tokamak
  crossref Yu. V. Kovalenko, P. V. Zubarev, S. V. Ivanenko, A. L. Solomakhin 等 2025-01-23T18:03:39Z 置信度 0.70
• Impact of Resonant Helical Magnetic Fields on the Correlations between Density Bursts and Magnetic Fluctuation in IR-T1 Tokamak
  crossref M. Mahjour, M. Lafouti, M. Ghoranneviss, M. K. Salem 2025-02-17T19:38:48Z 置信度 0.70
• Large-database cross-verification and validation of tokamak transport models using baselines for comparison
  State-of-the-art 1D transport solvers ASTRA and TRANSP are verified, then validated across a large database of semi-randomly selected, time-dependent DIII-D discharges. Various empirical models are provided as baselines to contextualize the validation figures …
  crossref J. Abbate, E. Fable, B. Grierson, A. Pankin 等 2024-04-11T12:50:10Z 置信度 0.70
• Определение рабочей области корреляционного рефлектометра на токамаке Т-15МД.
  crossref A. Loginov, D. Shelukhin, V. Vershkov, I. Vladimirov 2024-09-04T19:44:32Z 置信度 0.70
• Система коллимации жесткого рентгеновского излучения на токамаке Т-15МД.
  crossref V.I. Tepikin, E.A. Shestakov, P.V. Savrukhin, P.D. Lisovoy 等 2024-09-04T19:44:32Z 置信度 0.70
• A Model-Based Reference Governor for the Control of the Plasma Shape in the Tcv Tokamak
  crossref Adriano Mele, Alessandro Tenaglia, Federico Felici, Cristian Galperti 等 2024-11-09T14:37:31Z 置信度 0.70
• Modeling and meshing for tokamak edge plasma simulations
  crossref Usman Riaz, E. Seegyoung Seol, Robert Hager, Mark S. Shephard 2023-10-26T21:02:55Z 置信度 0.70
• Error field penetration in J-TEXT tokamak based on two-fluid drift-MHD model
  An externally generated resonant magnetic perturbation can induce complex non-ideal MHD responses in their resonant surfaces. We have studied the plasma responses using Fitzpatrick’s improved two-fluid model and program LAYER. We calculated the error field pen…
  crossref Wen 文 Wang 王, Tao 涛 Xu 徐, Yi 仪 Zhang 张 2024-01-15T10:42:28Z 置信度 0.70
• Effect of symmetry-breaking on the MHD edge stability limit of tokamak plasmas
  Abstract We demonstrate for the first time that symmetry-breaking in tokamak plasmas reduces the window of stable edge operational space, leading to a lower achievable edge pressure gradient. Predictive simulations with the linear magnetohydrodynamic stability…
  crossref J. Puchmayr, M. Dunne, E. Strumberger, M. Willensdorfer 等 2024-06-06T22:21:50Z 置信度 0.70
• Final Development and Preliminary Experiment Progress of In-Vessel Resonant Magnetic Perturbation Coils System on Hl-3 Tokamak
  This paper details the design, construction, and analysis of resonant magnetic perturbation (RMP) with 16 in-vessel coils on the HL-3 to investigate the interactions between resonant magnetic perturbations and magnetohydrodynamic instabilities. The toroidal × …
  crossref Ao Wang, Tengfei Sun, WEI CHEN, Butian Cui 等 2024-08-19T05:51:28Z 置信度 0.70
• Thermal Hydraulic and Material Analysis of Upgraded Flat-Type Divertor Mock-Up for Pakistan Spherical Tokamak (Pst)
  crossref shahab uddin khan, Ayesha Alam, Abdullah Muhammad, Ahmad Ali 等 2024-07-04T19:47:39Z 置信度 0.70
• Retraction Note: Measurement of Plasma Energy Confinement Time in Presence of Resonant Helical Field in IR-T1 Tokamak
  crossref A. Salar Elahi, M. Ghoranneviss 2024-07-18T02:01:46Z 置信度 0.70
• Design and analysis of redundant electro-hydraulic-driven manipulator for tokamak vacuum vessel
  crossref Daoan Kang, Bangmeng Wang, Chao Huang, Dingan Song 等 2024-04-15T17:12:17Z 置信度 0.70
• Integral analysis of the effect of material dimension and composition on tokamak neutronics ^*
  Abstract The neutronics performance of a tokamak has been identified as an important factor in designing a fusion power plant. The design of the tokamak should not only meet operational parameters such as sufficient tritium breeding, but also safety parameters…
  crossref Jin Whan Bae, Davin Young, Katarzyna Borowiec, Vittorio Badalassi 2024-03-14T18:24:55Z 置信度 0.70
• Design of SIL-2 interlock function for tokamak fusion reactor
  The ITER Gas Injection System (GIS) Regulates fueling and impurity gases during plasma discharges within the tokamak vacuum vessel. To implement ITER investment protection, the GIS requires capable of interlock function to shielding the gases from ITER vacuum …
  crossref Zhengyang Gu, Yuxuan Zhao, Weixiang Gong, Xia Zhiwei 等 2024-05-21T23:41:00Z 置信度 0.70
• Retraction Note: Two Semi-Empirical Methods for Determination of Shafranov Shift in IR-T1 Tokamak
  crossref A. Salar Elahi, M. Ghoranneviss, A. Rahimi Rad 2024-07-02T05:04:47Z 置信度 0.70
• Retraction Note: Feedback System Design for Plasma Horizontal Position Control in IR-T1 Tokamak
  crossref A. Naghidokht, R. Khodabakhsh, M. Ghoranneviss, A. Salar Elahi 2024-10-09T03:02:04Z 置信度 0.70
• Main Nuclear Responses of the DEMO Tokamak with Different In-Vessel Component Configurations
  Research and development of the DEMOnstration power plant (DEMO) breeder blanket (BB) has been performed in recent years based on a predefined DEMO tritium breeding ratio (TBR) requirement, which determines a loss of wall surface due to non-breeding in-vessel …
  crossref Jin Hun Park, Pavel Pereslavtsev 2024-01-23T08:28:28Z 置信度 0.70
• Retraction Note: Experimental Study of Effects of the Internal Inductance on the Energy Confinement Time in IR-T1 Tokamak
  crossref A. Salar Elahi, M. Ghoranneviss 2024-07-20T01:02:15Z 置信度 0.70
• Design of a Robust $H_{\infty}$ Plasma Position Controller for Aditya-U Tokamak
  crossref Sachin Kumar, Bidyadhar Subudhi, Rohit Kumar 2025-04-21T17:35:35Z 置信度 0.70
• Development and application of a predictive model for advanced tokamak scenario design
  Abstract Advanced tokamak (AT) scenarios applying additional heating during the current ramp (early-heating) usually require many iterations if developed fully empirically. To reduce the required experimental time, a model has been developed in the ASTRA frame…
  crossref Raphael Schramm, Alexander Bock, Emiliano Fable, Jörg Stober 等 2024-01-19T09:40:36Z 置信度 0.70
• Measurements of microwave transmission mode in HL-3 tokamak relevant ECH corrugated waveguides transmission line
  crossref Guoyao Fan, Mei Huang, Donghui Xia, Cheng Chen 等 2024-09-29T01:59:26Z 置信度 0.70
• Real-time control of NBI fast ions, current-drive and heating properties
  Abstract Conventionally, neutral beam injection (NBI) in tokamaks is controlled via engineering parameters such as injection voltage and power. Recently, the high-fidelity real-time NBI code RABBIT has been coupled to the discharge control system of ASDEX Upgr…
  crossref M. Weiland, O. Kudlacek, B. Sieglin, R. Bilato 等 2024-02-19T17:30:07Z 置信度 0.70
• Decoupled magnetic control of spherical tokamak divertors via vacuum harmonic constraints
  Abstract Power exhaust is a critical challenge for spherical tokamak reactors, making the design, optimisation and control of advanced divertor configurations crucial. These tasks are greatly simplified if the poloidal magnetic fields in the core and divertor …
  crossref O P Bardsley, J L Baker, C Vincent 2024-03-08T16:00:42Z 置信度 0.70
• Divertor turbulent transport in the single null and snowflake in the TCV tokamak
  The relative importance of divertor radial turbulent particle fluxes is considered by comparing it against the fluxes in the main-chamber outer midplane (OMP) in a variety of conditions and divertor geometries in the tokamak à configuration variable. Within th…
  crossref C. K. Tsui, J. A. Boedo, J. R. Myra, D. Galassi 等 2024-02-16T19:42:14Z 置信度 0.70
• Retraction Note to: Measurement of the Shafranov Parameter in Presence of the Toroidal Field Ripple in IR-T1 Tokamak
  crossref A. Salar Elahi, M. Ghoranneviss 2024-07-04T11:02:33Z 置信度 0.70
• DOE Final Report on Virginia Tech’s contribution to “Tokamak Disruption Simulation”
  crossref Bhuvana Srinivasan 2025-06-12T22:17:26Z 置信度 0.70
• Retraction Note to: Effects of Alfvenic Poloidal Flow and External Vertical Field on Plasma Position in IR-T1 Tokamak
  crossref A. Salar Elahi, M. Ghoranneviss 2024-07-04T11:02:33Z 置信度 0.70
• 3D radiated power analysis of JET SPI discharges using the Emis3D forward modeling tool
  Precise values for radiated energy in tokamak disruption experiments are needed to validate disruption mitigation techniques for burning plasma tokamaks like ITER and SPARC. Control room analysis of radiated power (Prad) on JET assumes axisymmetry, since fitti…
  datacite B. Stein-Lubrano, R. Sweeney, D. Bonfiglio, J. Lovell, P. Carvalho, L. Baylor, R.S. Granetz, S. Jachmich, E. Joffrin, M. Kong, M. Lehnen, C. Maggi, E. Marmar, E. Nardon, P. Puglia, U. Sheikh, D. Shiraki, S. Silburn, Jet Contributors 2025 置信度 0.66 PhysicsbolometryCherabdisruptionJET
• Data used to obtain multiple GS solutions on MAST-U with FreeGSNKE
  The Grad–Shafranov (GS) equation is a nonlinear elliptic partial differential equation that governs the ideal magnetohydrodynamic equilibrium of a tokamak plasma. Previous studies have demonstrated the existence of multiple solutions to the GS equation when so…
  datacite Pentland, Kamran, Amorisco, Nicola, Farrell, Patrick, Ham, Christopher 2025 置信度 0.66 Multiple solutionsGrad-ShafranovMHD equilibriaFreeGSNKEDeflated continuation
• Design solutions for the hodoscope of the magnetic proton recoil neutron spectrometer of the SPARC tokamak
  A new 14 MeV neutron spectrometer utilizing the magnetic proton recoil (MPR) technique is under development for the SPARC tokamak. This instrument measures neutrons by converting them into protons, whose momenta are subsequently analyzed using a series of magn…
  datacite Rosa, M.D.; Mackie, S.; Rigamonti, D.; Tedoldi, L.G.; Colombi, S.; Molin, A.D.; Marcer, G.; Nocente, M.; Gorini, G.; Raj, P.; Rebai, M.; Carmichael, J.; Reinke, M.; Scioscioli, F.; Tinguely, R.A.; Tardocchi, M. 2025 置信度 0.66 PhysicsEJ276D scintillation rodelectron volt energy 14.0 MeVhodoscope detectorsmagnetic proton recoil neutron spectrometer
• Neutronics simulations for the design of neutron flux monitors in SPARC
  This paper presents the development and application of high-fidelity neutronic models of the SPARC tokamak for the design of neutron flux monitors (NFM) during plasma operations. NFMs measure the neutron flux in the tokamak hall which is related to fusion powe…
  datacite Wang, X.; Gocht, R.; Ball, J.; Mackie, S.; Panontin, E.; Tinguely, R.A.; Raj, P.; Holmes, I.; Saltos, A.A.; Johnson, A.; Grieve, A. 2025 置信度 0.66 PhysicsB10 ICborated HDPE housingsborated HDPE sleeveboron-10 gamma-compensated ionization chambers
• Latent Space Mapping: Revolutionizing Predictive Models for Divertor Plasma Detachment Control
  The inherent complexity of boundary plasma, characterized by multi-scale and multi-physics challenges, has historically restricted high-fidelity simulations to scientific research due to their intensive computational demands. Consequently, routine applications…
  datacite Zhu, Ben, Zhao, Menglong, Xu, Xue-Qiao, Gupta, Anchal 等 2025 置信度 0.66 Plasma Physics (physics.plasm-ph)Computational Physics (physics.comp-ph)FOS: Physical sciencesFOS: Physical sciences
• Investigation of Tearing Mode Stability Near Ideal Stability Boundaries Via Asymptotic Matching Techniques
  A number of improvements to the TJ toroidal tearing mode code [Phys. Plasmas 31, 102507 (2024)] are documented. The TJ code is also successfully benchmarked against the STRIDE toroidal tearing mode code [Phys. Plasmas 25, 082502 (2018)]. Finally, the new capab…
  datacite Fitzpatrick, Richard 2025 置信度 0.66 Plasma Physics (physics.plasm-ph)FOS: Physical sciencesFOS: Physical sciences
• Computation of generalised magnetic coordinates asymptotically close to the separatrix
  Integrals to calculate generalised magnetic coordinates from an input magnetic flux function asymptotically close to the separatrix are presented, and implemented in the GPEC/DCON code suite. These integrals allow characterisation of the magnetic equilibrium o…
  datacite Benjamin, Stuart, Logan, Nikolas, Hansen, Christopher 2025 置信度 0.66 Plasma Physics (physics.plasm-ph)FOS: Physical sciencesFOS: Physical sciences
• Public Data Set: Erratum: “Initial Characterization of Electron Temperature and Density Profiles in PEGASUS Spherical Tokamak Discharges Driven Solely by Local Helicity Injection” [Phys. Plasmas 28, 102504 (2021)]
  This public data set contains openly-documented, machine readable digital research data corresponding to figures published in G.M. Bodner et al., ‘Erratum: “Initial Characterization of Electron Temperature and Density Profiles in PEGASUS Spherical Tokamak Disc…
  datacite Bodner, Grant, Bongard, Michael, Fonck, Raymond, Goetz, John 等 2024 置信度 0.66 70 PLASMA PHYSICS AND FUSION TECHNOLOGY
• Public Data Set: Initial Characterization of Electron Temperature and Density Profiles in PEGASUS Spherical Tokamak Discharges Driven Solely by Local Helicity Injection
  This public data set contains openly-documented, machine readable digital research data corresponding to figures published in G.M. Bodner et al., ‘Initial Characterization of Electron Temperature and Density Profiles in PEGASUS Spherical Tokamak Discharges Dri…
  datacite Bodner, Grant, Bongard, Michael, Fonck, Raymond, Goetz, John 等 2024 置信度 0.66 70 PLASMA PHYSICS AND FUSION TECHNOLOGY
• An accurate SUPG-stabilized continuous Galerkin discretization for anisotropic heat flux in magnetic confinement fusion
  We present a novel spatial discretization for the anisotropic heat conduction equation, aimed at improved accuracy at the high levels of anisotropy seen in a magnetized plasma, for example, for magnetic confinement fusion. The new discretization is based on a …
  datacite Wimmer, Golo A., Southworth, Ben S., Sagiyama, Koki, Tang, Xian-Zhu 2024 置信度 0.66 Numerical Analysis (math.NA)FOS: MathematicsFOS: Mathematics
• Public Data Set: Effects of Injected Current Streams on MHD Equilibrium Reconstruction of Local Helicity Injection Plasmas in a Spherical Tokamak
  This public data set contains openly-documented, machine readable digital research data corresponding to figures published in J.D. Weberski et al., 'Effects of Injected Current Streams on MHD Equilibrium Reconstruction of Local Helicity Injection Plasmas in a …
  datacite Weberski, Justin, Bongard, Michael, Diem, Stephanie, Fonck, Raymond 等 2024 置信度 0.66 70 PLASMA PHYSICS AND FUSION TECHNOLOGYLocal Helicity Injection, Equilibrium Reconstruction, Solenoid-free Tokamak Startup, Non-axisymmetric Perturbation
• A research program to measure the lifetime of spin polarized fuel
  The use of spin polarized fuel could increase the deuterium-tritium (D-T) fusion cross section by a factor of 1.5 and, owing to alpha heating, increase the fusion power by an even larger factor.Issues associated with the use of polarized fuel in a reactor are …
  datacite Heidbrink, W. W., Baylor, L. R., Büscher, M., Engels, R. W. 等 2024 置信度 0.66
• Multi-objective Bayesian optimization for design of Pareto-optimal current drive profiles in STEP
  The safety factor profile is a key property in determining the stability of tokamak plasmas. To design the safety factor profile in the United Kingdom's proposed Spherical Tokamak for Energy Production (STEP), we apply multi-objective Bayesian optimisation to …
  datacite Brown, Theodore, Marsden, Stephen, Gopakumar, Vignesh, Terenin, Alexander 等 2023 置信度 0.66 Plasma Physics (physics.plasm-ph)FOS: Physical sciencesFOS: Physical sciences
• Understanding Large-Scale Plasma Simulation Challenges for Fusion Energy on Supercomputers
  Understanding plasma instabilities is essential for achieving sustainable fusion energy, with large-scale plasma simulations playing a crucial role in both the design and development of next-generation fusion energy devices and the modelling of industrial plas…
  datacite Williams, Jeremy J., Bhole, Ashish, Kierans, Dylan, Hoelzl, Matthias 等 2024 置信度 0.66 Plasma Physics (physics.plasm-ph)Distributed, Parallel, and Cluster Computing (cs.DC)Performance (cs.PF)Computational Physics (physics.comp-ph)FOS: Physical sciences
• Implementation of matrix compression in the coupling of JOREK to realistic 3D conducting wall structures
  JOREK is an advanced non-linear simulation code for studying MHD instabilities in magnetically confined fusion plasmas and their control and/or mitigation. A free-boundary and resistive wall extension was introduced via coupling to the STARWALL and CARIDDI cod…
  datacite Cipolletta, Federico, Schwarz, Nina, Hoelzl, Matthias, Ventre, Salvatore 等 2024 置信度 0.66 Plasma Physics (physics.plasm-ph)FOS: Physical sciencesFOS: Physical sciences
• Low latency optical-based mode tracking with machine learning deployed on FPGAs on a tokamak
  Active feedback control in magnetic confinement fusion devices is desirable to mitigate plasma instabilities and enable robust operation. Optical high-speed cameras provide a powerful, non-invasive diagnostic and can be suitable for these applications. In this…
  datacite Wei, Yumou, Forelli, Ryan F., Hansen, Chris, Levesque, Jeffrey P. 等 2023 置信度 0.66 Plasma Physics (physics.plasm-ph)Hardware Architecture (cs.AR)Machine Learning (cs.LG)Instrumentation and Detectors (physics.ins-det)FOS: Physical sciences
• Detection and tracking of turbulent structures in the edge of tokamak plasmas using machine learning
  This repository contains the data used in the study entitled "Detection and tracking of turbulent structures in the edge of tokamak plasmas: use of an ultra-fast camera and comparison of machine learning and Kalman filter methods". The data was collected using…
  datacite Chouchene, Sarah, brochard, frédéric, Lemoine, Nicolas, Cavalier, Jordan 2024 置信度 0.66
• Detection and tracking of turbulent structures in the edge of tokamak plasmas using machine learning
  This repository contains the data used in the study entitled "Detection and tracking of turbulent structures in the edge of tokamak plasmas: use of an ultra-fast camera and comparison of machine learning and Kalman filter methods". The data was collected using…
  datacite Chouchene, Sarah, brochard, frédéric, Lemoine, Nicolas, Cavalier, Jordan 2024 置信度 0.66
• A research program to measure the lifetime of spin polarized fuel
  The use of spin polarized fuel could increase the deuterium-tritium (D-T) fusion cross section by a factor of 1.5 and, owing to alpha heating, increase the fusion power by an even larger factor. Issues associated with the use of polarized fuel in a reactor are…
  datacite Heidbrink, W. W., Baylor, L. R., Büscher, Markus, Engels, Ralf W. 等 2024 置信度 0.66 530
• Fluid and kinetic studies of tokamak disruptions using Bayesian optimization
  The codes and the data in this directory corresponds to the code and results used in the paper [I. Ekmark et al (2024) J. Plasma Phys., Fluid and kinetic studies of tokamak disruptions using Bayesian optimization, http://arxiv.org/abs/2402.05843]. References t…
  datacite Ekmark, Ida, Hoppe, Mathias, Fülöp, Tünde, Jansson, Patrik 等 2024 置信度 0.66 DisruptionsBayesian OptimizationFluid modelingKinetic modelingPlasma
• Fluid and kinetic studies of tokamak disruptions using Bayesian optimization
  The codes and the data in this directory corresponds to the code and results used in the paper [I. Ekmark et al (2024) J. Plasma Phys., Fluid and kinetic studies of tokamak disruptions using Bayesian optimization, http://arxiv.org/abs/2402.05843]. References t…
  datacite Ekmark, Ida, Hoppe, Mathias, Fülöp, Tünde, Jansson, Patrik 等 2024 置信度 0.66 DisruptionsBayesian OptimizationFluid modelingKinetic modelingPlasma
• Shell scripts to support running MELCOR within batch systems
  Shell scripts to enable running of MELCOR software within a batch system such as SGE, described in the paper \\"Reducing The User Burden When Running MELCOR For Accident Analysis For A Tokamak\\" Fusion Engineering and Design 202 (2024) 114399.
  datacite Nebrensky, Jindrich, Karajgikar, Gowri 2024 置信度 0.66 shell scriptMELCOR
• Kinetic-Ballooning-Limited Pedestals in Spherical Tokamak Plasmas
  A theoretical model is presented that for the first time matches experimental measurements of the pedestal width-height Diallo scaling in the low-aspect-ratio high-$β$ tokamak NSTX. Combining linear gyrokinetics with self-consistent pedestal equilibrium variat…
  datacite Parisi, J. F., Guttenfelder, W., Nelson, A. O., Gaur, R. 等 2023 置信度 0.66 Plasma Physics (physics.plasm-ph)FOS: Physical sciencesFOS: Physical sciences
• Control System Design of the CHIMERA Fusion Test Facility
  CHIMERA is an experimental nuclear fusion test facility which aims to simulate the intense magnetic fields and temperature gradients found within a tokamak fusion reactor. The control system at CHIMERA is based on EPICS and will have approximately 30 input/out…
  datacite Smith, Philip, Greer, Alan, McCubbin, David, Roberts, Bryn 等 2024 置信度 0.66 Accelerator PhysicsSoftware
• First principles simulation of early stage plasma initiation process in ITER-scale tokamak
  A first principles 6D kinetic model is developed to study the earliest times of unassisted plasma breakdown in an International Thermonuclear Experimental Reactor (ITER)-scale tokamak. This is then used for a comparative study of the predicted ionisation rate …
  datacite Chew, Junxian, Gibbon, Paul, Brömmel, Dirk, Wauters, Tom 等 2024 置信度 0.66 620
• Efda–Jet–Pr(13)04 Real-Time Algorithms For Jet Hard X-Ray And Gamma-Ray Profile Monitor
  ABSTRACT The steady state operation with high energy content foreseen for future generation of fusion devices will necessarily demand dedicated real-time tools and mechanisms for data handling and machine control. Consequently, the real-time systems for those …
  datacite A. Fernandes1, R.C. Pereira1 2013 置信度 0.66
• Design and Analysis of Redundant Electro-Hydraulic-Driven Manipulator for Tokamak Vacuum Vessel
  crossref Daoan Kang, Bangmeng Wang, Chao Huang, Dingan Song 等 2024-02-01T11:28:16Z 置信度 0.70
• Transp Integrated Modeling Code for Interpretive and Predictive Analysis of Tokamak Plasmas
  crossref Alexei Y. Pankin, Joshua Breslau, Marina Gorelenkova, Robert Andre 等 2024-07-26T14:17:21Z 置信度 0.70
• High precision phase difference calculation based on adaptive mixed-radix All-phase FFT for Tokamak plasma electron density measurement
  Abstract In many Tokamak devices, laser interferometers, such as HCN, DCN, CO2, etc, are employed to measure the plasma electron density by calculating the phase difference between the reference signal and the detector signal. This paper proposes an adaptive A…
  crossref Shuangbao Shu, Jin Lai, Yong Wang, Shanlin Liu 2024-10-10T14:35:51Z 置信度 0.70
• Pumping System of the Vacuum Chamber of the Tokamak T-15MD Unit
  crossref I. O. Anashkin, V. A. Kochin, I. S. Obraztsov 2025-01-10T19:47:19Z 置信度 0.70
• Correction: Optimizing 3D magnetic perturbations for edge instability control in the KSTAR tokamak
  crossref Jong-Kyu Park 2024-03-16T03:02:27Z 置信度 0.70
• Retraction Note: Evolution of the IR-T1 Tokamak Plasma Local and Global Parameters
  crossref A. Salar Elahi, M. Ghoranneviss 2024-07-04T11:02:33Z 置信度 0.70
• Моделирование переноса нейтралов вольфрама в лимитерной плазме токамака.
  crossref A.A. Kozhurin, R.R. Khayrutdinov, V.E. Lukash 2024-09-04T19:44:32Z 置信度 0.70
• Full-f gyrokinetic simulations of hydrogen isotope mixing in tokamak plasmas
  Hydrogen isotope mixing phenomena in tokamak plasmas are analyzed using global full-f gyrokinetic simulations. Model plasma parameters are chosen based on hydrogen isotope pellet experiments on JET, in which fast hydrogen isotope mixing in the timescale of the…
  crossref Y. Idomura 2024-10-09T12:42:09Z 置信度 0.70
• Approach to spatial integration on a novel and complex major project – STEP concept Tokamak
  crossref Adam Woods, Alex Hellend, Jonathan Keep, Emily Kimbrey 等 2024-03-14T16:07:50Z 置信度 0.70
• Large-scale relativistic calculations of spectral data in Zr XXVIII, Nb XXIX and Tc XXXI of tokamak interest
  crossref Z.B. Chen 2024-05-02T12:37:00Z 置信度 0.70
• Advanced surrogate model for electron-scale turbulence in tokamak pedestals
  We derive an advanced surrogate model for predicting turbulent transport at the edge of tokamaks driven by electron temperature gradient (ETG) modes. Our derivation is based on a recently developed sensitivity-driven sparse grid interpolation approach for unce…
  crossref Ionuţ-Gabriel Farcaş, Gabriele Merlo, Frank Jenko 2024-10-28T07:02:40Z 置信度 0.70
• Estimation of Plasma Vertical Position by Long-Short Term Memory Network with Time2Vec in a Small Tokamak Device PHiX
  crossref Sejung JANG, Hiroaki TSUTSUI 2024-08-02T22:14:03Z 置信度 0.70
• Upgrade and validation of the radio frequency magnetic probe array system on experimental advanced superconducting tokamak
  crossref Guanghou Yan, Bojiang Ding, Chenbin Chenbin, Miaohui Li 2024-08-07T16:18:35Z 置信度 0.70
• Implications of Particle Recycling on Core Plasma Performance in Advanced Aneutronic Fuel Spherical Tokamak Reactor
  crossref M. Maleki, S. M. Motevalli, F. Fadaei 2024-02-06T14:02:26Z 置信度 0.70
• Magnetic Component of Quasi-Coherent Mode of Plasma Fluctuations in Ohmic Plasma of the T-10 Tokamak
  In this work the phenomenon of the quasi-coherent mode of plasma fluctuations in purely ohmic plasmas of the T-10 tokamak is investigated. The plasma magnetic fluctuation spectra along with spectra of relative electron density oscillations and plasma potential…
  crossref N. S. Sergeev, A. V. Melnikov, L. G. Eliseev 2024-05-28T14:02:08Z 置信度 0.70
• Emulation techniques for scenario and classical control design of tokamak plasmas
  The optimization of scenarios and design of real-time-control in tokamaks, especially for machines still in design phase, requires a comprehensive exploration of solutions to the Grad–Shafranov (GS) equation over a high-dimensional space of plasma and coil par…
  crossref A. Agnello, N. C. Amorisco, A. Keats, G. K. Holt 等 2024-04-02T14:00:43Z 置信度 0.70
• Enhanced pressure control system for the vacuum vessel of Damavand Tokamak using PID and multiple model control
  crossref Mahdi Amini, Mahdi Aliyari Shoorehdeli, Hossein Rasouli 2024-02-02T01:42:56Z 置信度 0.70
• Preliminary Results of Non-Evaporable Getter Pumps Studies and First Test in East Tokamak
  crossref Chao Wang, Yaowei Yu, Hao Sun, Bin Cao 等 2024-01-15T17:18:26Z 置信度 0.70
• Preliminary design of an AXUV photodiode-based bolometer camera for MT-I spherical tokamak
  crossref Azam Hussain, Shah Zaib Zahid, M. Aqib Javed, Riaz Khan 2024-05-01T00:28:19Z 置信度 0.70
• Power Balance in TOKASTAR-2 Small Tokamak for Feasibility Study on Light Source Application
  crossref A. Okamoto, S. Kimata, K. Tsunoda, K. Kado 等 2024-12-27T20:49:18Z 置信度 0.70
• Retraction Note To: Plasma Horizontal Displacement Measurement Using Flux Loops in IR-T1 Tokamak
  crossref A. Salar Elahi, M. Ghoranneviss 2024-07-08T03:02:10Z 置信度 0.70
• Investigation of impulse voltage test of ohmic coil system in ADITYA-U tokamak
  crossref Rohit Kumar, Harshita Raj, R.L. Tanna, Tanmay Macwan 等 2024-02-06T10:31:22Z 置信度 0.70
• Gyrokinetic Calculations of Heat Fluxes in the T-10 Tokamak Ohmic Discharge
  crossref M. Yu. Isaev, O. Anuaruly, A. Yu. Kuyanov, D. B. Smirnov 2024-09-22T09:01:28Z 置信度 0.70
• Methodology for Calculating the Hydrogen Isotope Inventory in Tritium Fuel Cycle Systems of the DEMO-FNS Tokamak
  crossref S. S. Ananyev, B. V. Ivanov 2025-01-10T19:47:28Z 置信度 0.70
• Stable voltage control of a 300MVA motor generator for HL-3 tokamak
  crossref Yulin Xu, Jianfei Peng, Yingqiao Wang, Huajun Li 等 2024-06-07T14:32:10Z 置信度 0.70
• Development of an MDSPlus-based Data Acquisition and Management System for Tokamak Devices
  crossref Shuangbao Shu, Ziqiang Yang, Shurui Zhang, Jiyao Wang 等 2025-02-03T14:05:04Z 置信度 0.70
• Computational Study of the Supersonic Molecular Beam Injection in Thailand Tokamak-1 based on the 2D Fluid Model
  crossref Kitti RONGPUIT, Apiwat WISITSORASAK, Jiraporn PROMPING 2024-01-18T22:12:23Z 置信度 0.70
• Analyses of Particle and Energy Balances using a Core-SOL-Divertor (CSD) Model for Tokamak DEMO-Reactor Studies
  crossref Kazuhiro YAMADA, Kazuo HOSHINO, Akiyoshi HATAYAMA 2024-11-25T22:15:54Z 置信度 0.70
• Retraction Note: RHF Effect on Shafranov Parameter and Shafranov Shift in IR-T1 Tokamak
  crossref A. Salar Elahi, M. Ghoranneviss 2024-07-20T01:02:15Z 置信度 0.70