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Beam transmission design for a 120 keV and 15 MW neutral beam injection system for burning plasma tokamak
Plasma Physics and Controlled FusionAbstract For tokamak devices, neutral beam injection (NBI) remains an important method for heating and current drive. In this paper, the beam transmission model based on positive ion source neutral beam injector (P-NBI) is constructed using the Monte Carlo…
The Roadmap for runaway electron-induced plasma facing component damage in tokamaks
Plasma Physics and Controlled FusionAbstract This Roadmap article addresses the critical and multifaceted challenge of plasma-facing component (PFC) damage caused by runaway electrons (REs) in tokamaks, a phenomenon that poses a significant threat to the viability and longevity of future fusi…
Energetic particle driven Alfvén eigenmodes and associated energetic particle redistribution in a tokamak burning plasma
Nuclear FusionAbstract Energetic-particle driven Alfvén eigenmodes (AEs) and associated redistribution of energetic particles in phase space are investigated using kinetic-magnetohydrodynamic (MHD) hybrid simulations for a tokamak burning plasma with weakly reversed magn…
An Overview of Magnetic Confinement Fusion:Tokamak, Stellarator, Reversed-Field Pinch, Field-Reversed Configuration, Magnetic Mirror
SuperconductivityMagnetic confinement fusion (MCF) is widely regarded as a promising pathway toward achieving sustainable and large-scale clean energy production. This paper presents a comprehensive review of the fundamental principles, major configurations, historical evol…
Readiness of Tritium Handling Technology for Fusion Energy Systems
Fusion Science & TechnologyAt the present time more than 50 companies have undertaken the quest to develop fusion energy systems using a variety of approaches including magnetic confinement schemes such as tokamaks, stellarators, reverse field configurations, mirrors, and inertial co…
MHD, disruptions and control physics: Chapter 4 of the special issue: on the path to tokamak burning plasma operation
Nuclear FusionAbstract In this chapter, we review the progress in MHD stability, disruptions and control in magnetic fusion research that has occurred over the past (more than) one and a half decades since the publication by Hender et al in 2007 on the same topic as part…
Upgrades and characteristics of the compact torus injector for central fueling of the EAST tokamak
Plasma Science and TechnologyAbstract The compact torus injector (CTI) for the central fueling of the EAST tokamak has undergone significant upgrades to enhance its injection capability. During the initial phase of the platform testing phase, EAST-CTI demonstrated relatively low perfor…
Runaway electron-induced plasma facing component damage in tokamaks
arXivThis Roadmap article addresses the critical and multifaceted challenge of plasma-facing component (PFC) damage caused by runaway electrons (REs) in tokamaks, a phenomenon that poses a significant threat to the viability and longevity of future fusion reacto…
Suppression of Runaway Electron Current During a Discharge Disruption in an ITER-Scale Tokamak of Using an Injected Collector
Plasma Physics ReportsAbstract This paper presents the results of numerical simulations of the time evolution of plasma current and the suppression of the runaway electron current in an ITER-scale tokamak during the disruption of the tokamak discharge by means of injection of tu…
Design and conceptual modeling of a tokamak-like X-point divertor for the Helios quasi-axisymmetric stellarator
Fusion Engineering and DesignA novel divertor solution is presented for a pre-conceptual design point of the quasi-axisymmetric stellarator power plant, “Helios.” This solution, isomorphic to the poloidal divertor in a tokamak, features a toroidally-continuous n=0, m=2 double null conf…
Workforce Expansion in the Inertial Fusion Science and Technology (RISE) Hub for Inertial Fusion Energy
Fusion Science & TechnologyWith the rapid growth and development of potential commercial fusion power plants, the urgency of building a skilled workforce is increasing. Therefore, it is necessary to train and educate early-career scientists and engineers to be able to work for curren…
Progress in the pre-conceptual design of the auxiliary heating and current drive system for the Tokamak Energy Fusion Pilot Plant
EPJ Web of ConferencesAuxiliary heating and current drive is a crucial aspect of reactor-relevant tokamaks. Tokamak Energy is currently in the design phase of their Fusion Pilot Plant (FPP). Initial investigations for the flat-top phase of plasma scenarios rely exclusively on el…
CHINA’S EAST TOKAMAK PROGRAM AND THE EFFECTS OF FUSION ENERGY ON ENERGY IMPORT DEPENDENCY: A STRATEGIC ASSESSMENT FOR TURKEY
Yönetim ve Ekonomi Araştırmaları DergisiThis study assesses the implications of fusion energy for energy-import-dependent economies by examining China’s Experimental Advanced Superconducting Tokamak program and its relevance for Turkey. A qualitative research design is employed, combining a syste…
Gyrokinetic Simulations for Spherical Tokamak Divertor Design
arXiv (Cornell University)Nuclear fusion is an attractive source of energy because the fuel is abundant and it produces low levels of carbon emissions. The tokamak, which confines a plasma using magnetic fields, is the most mature nuclear fusion reactor concept. Maximizing energy co…
Energetic particle physics: Chapter 7 of the special issue: on the path to tokamak burning plasma operation
Nuclear FusionAbstract We review the physics of energetic particles (EPs) in magnetically confined burning fusion plasmas with focus on advances since the last update of the ITER Physics Basis (Fasoli et al 2007 Nucl. Fusion 47 S264). Topics include basic EP physics, EP…
Tokamak level performance in the optimized stellarator Wendelstein 7-X with stable peaked density profiles
Physical review. EProgress towards achieving net gain from nuclear fusion is typically characterized by the triple product n T τ . Although stellarators have several benefits for a reactor, such as the inherent steady-state capability and the lack of disruptions, the maximum…
Integrated Neutronics Modeling for Inertial Fusion Energy Systems: Development and Application to LD-FIRST
IEEE Transactions on Plasma ScienceLawrence Livermore National Laboratory (LLNL) is proposing a new Laser Driven Fusion Integration Research and Science Test Facility (LD-FIRST) with the goal of providing an experimental testbed for future Inertial Fusion Energy (IFE) systems. However, IFE s…
Model-based estimation of tokamak plasma profiles and physics parameters: algorithm overview and application to ITER
Nuclear FusionAbstract Combining dynamic models and measurements into a consistent plasma state estimate is an important challenge for ITER and DEMO, due to the inherent limitations regarding diagnostic coverage in a nuclear fusion reactor environment. In this work, a mo…
On lower hybrid current drive in high magnetic field fusion reactor level tokamaks
Nuclear FusionAbstract This paper mainly studies the effects of high magnetic field and quasi-linear effects on lower hybrid current drive (LHCD) in fusion reactor-level tokamak. The critical magnetic field B c value for LHCD is 9.64 T. Below this value, high magnetic fi…
STORM: Scrape-off layer turbulence in tokamak fusion reactors
Computer Physics CommunicationsThe scrape-off layer of a tokamak fusion reactor carries the plasma exhaust from the hot core plasma to the material surfaces of the reactor vessel. The heat loads imposed by the exhaust are a critical limit on the performance of fusion power plants. Turbul…
Progress in pedestal and edge physics: Chapter 3 of the special issue: on the path to tokamak burning plasma operation
Nuclear FusionAbstract This paper describes the extensive progress that has been made in the understanding of tokamak pedestal physics since the 2007 publication of ‘Progress in the ITER Physics Basis’ (Ikeda 2007 Nucl. Fusion 47 E01–S500). It serves as Chapter 3 of the…
yancc: A GPU-accelerated, differentiable solver for neoclassical transport in tokamaks and stellarators
arXiv (Cornell University)We present yancc, a new GPU-accelerated solver for the drift kinetic equation that computes neoclassical transport fluxes, flows, and currents in tokamaks and stellarators. The drift kinetic equation is challenging to solve numerically due to strong advecti…
Development, Verification, and Validation of an OpenFOAM-Based Solver for Modeling Inertial Fusion Energy Chambers
Fusion Science & TechnologyOur work seeks to introduce a computational tool tailored to the physics of inertial fusion energy chambers, in particular, those concepts based on thick liquid walls. In this approach, the structural materials are protected by several neutron mean-free-pat…
Plasma Ramp-up and Sustainment Scenarios for Tokamak Energy’s Fusion Pilot Plant
EPJ Web of ConferencesTokamak Energy is designing a Fusion Pilot Plant under the US Department of Energy’s Milestone-Based Fusion Development Program. Tokamak Energy’s Fusion Pilot Plant is based on low aspect ratio tokamak with high-temperature superconducting coils, exploiting…