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Shielding materials in the compact spherical tokamak. [PDF]
Philos Trans A Math Phys Eng Sci, 2019 Neutron shielding materials are a critical area of development for nuclear fusion technology. In the compact spherical tokamak, shielding efficiency improvements are particularly needed because of severe space constraints. The most spatially restricted component is the central column shield.
Humphry-Baker SA, Smith GDW.
europepmc +5 more sources
Pulsed Spherical Tokamak—A New Approach to Fusion Reactors
Plasma, 2022 Traditionally, spherical tokamak (ST) reactors are considered to operate in a steady state. This paper analyses the advantages of a pulsed ST reactor.
Yuichi Takase
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A Neutron Source Based on Spherical Tokamak
EnergiesThe paper presents a conceptual study of a neutron source based on a spherical tokamak (ST). The plasma scenario chosen for the ST is non-thermal fusion (hot ion mode), which is extensively used on machines like JET and TFTR deuterium–tritium (DT ...
Francesco P. Orsitto +5 more
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Towards a compact spherical tokamak fusion pilot plant [PDF]
Philosophical Transactions Series A, Mathematical, Physical, and Engineering Sciences, 2019 A E Costley
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“PROCESS”: Systems studies of spherical tokamaks [PDF]
Fusion Engineering and Design, 2020 With a reduced aspect ratio, spherical tokamaks have a number of attractive features for a fusion power plant. This can be studied using systems codes, which allow for the rapid conceptual study of power plants covering everything, from the plasma through to electricity generation. In this paper, we describe models in the systems code PROCESS that have
Muldrew, Stuart I. +8 more
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Methodology of Plasma Shape Reachability Area Estimation in D-Shaped Tokamaks
Mathematics, 2022 This paper suggests and develops a new methodology of estimation for a multivariable reachability region of a plasma separatrix shape on the divertor phase of a plasma discharge in D-shaped tokamaks.
Yuri V. Mitrishkin +2 more
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Design of power supply system for the NanChang Spherical Tokamak
AIP Advances, 2022 The NanChang Spherical Tokamak (NCST), a new compact (plasma major radius R = 0.40 m, minor radius a = 0.24 m, and aspect ratio A = 1.67) spherical tokamak, is suitable for teaching and scientific research activities at the university. The principal goal
Ming Hou +4 more
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Overview of recent progress on steady state operation of all-metal plasma facing wall device QUEST
Nuclear Materials and Energy, 2021 QUEST (Q-shu university experiment with steady state spherical tokamak) is a midsize spherical tokamak capable of steady-state operation, comprising all-metal plasma-facing walls and a hot wall (HW) to address issues pertaining to fuel particle balance ...
K. Hanada +22 more
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Applied Sciences, 2023 In this study, we observed magnetohydrodynamic (MHD) activity of the spherical tokamak Globus-M2 which led to a deterioration in plasma confinement, such as a transition from the H-mode to L-mode, or even disruption.
Alexander Yashin +9 more
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Design of vacuum system for NCST spherical tokamak
AIP Advances, 2023 The NanChang Spherical Tokamak (NCST) is a new compact tokamak with an aspect ratio of R/a = 1.67. The vacuum system is one of the most important sub-systems of the tokamak device and has been designed especially for the NCST device. It consists of three
Fu Hua Huang +4 more
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