Blanket/first wall challenges and required R&D on the pathway to DEMO
The breeding blanket with integrated first wall (FW) is the key nuclear component for power
extraction, tritium fuel sustainability, and radiation shielding in fusion reactors. The ITER …
extraction, tritium fuel sustainability, and radiation shielding in fusion reactors. The ITER …
Progress in the development and understanding of a high poloidal-beta tokamak operating scenario for an attractive fusion pilot plant
S Ding, AM Garofalo - Reviews of Modern Plasma Physics, 2022 - Springer
The high poloidal-beta (β P) regime was first proposed as a high bootstrap current scenario
for a steady-state fusion pilot plant (FPP) in the 1990s (Kikuchi in Nucl Fusion 30: 265 …
for a steady-state fusion pilot plant (FPP) in the 1990s (Kikuchi in Nucl Fusion 30: 265 …
Japan's efforts to develop the concept of JA DEMO during the past decade
K Tobita, R Hiwatari, Y Sakamoto… - Fusion Science and …, 2019 - Taylor & Francis
This paper summarizes the evolution of Japanese DEMO design studies in a retrospective
manner by highlighting efforts to resolve critical design issues on DEMO. Japan is currently …
manner by highlighting efforts to resolve critical design issues on DEMO. Japan is currently …
First experimental tests of a new small angle slot divertor on DIII-D
A new small angle slot (SAS) divertor concept has been developed to enhance neutral
cooling across the divertor target by coupling a closed slot structure with appropriate target …
cooling across the divertor target by coupling a closed slot structure with appropriate target …
Evaluation of CFETR as a fusion nuclear science facility using multiple system codes
VS Chan, AE Costley, BN Wan, AM Garofalo… - Nuclear …, 2015 - iopscience.iop.org
This paper presents the results of a multi-system codes benchmarking study of the recently
published China Fusion Engineering Test Reactor (CFETR) pre-conceptual design (Wan et …
published China Fusion Engineering Test Reactor (CFETR) pre-conceptual design (Wan et …
Promising high-confinement regime for steady-state fusion
A reproducible stationary high-confinement regime with small “edge-localized
modes”(ELMs) has been achieved recently in the Experimental Advanced Superconducting …
modes”(ELMs) has been achieved recently in the Experimental Advanced Superconducting …
Small angle slot divertor concept for long pulse advanced tokamaks
SOLPS-EIRENE edge code analysis shows that a gas-tight slot divertor geometry with a
small-angle (glancing-incidence) target, named the small angle slot (SAS) divertor, can …
small-angle (glancing-incidence) target, named the small angle slot (SAS) divertor, can …
Core integrated simulations for the Divertor Tokamak Test facility scenarios towards consistent core-pedestal-SOL modelling
I Casiraghi, P Mantica, R Ambrosino… - Plasma Physics and …, 2023 - iopscience.iop.org
Deuterium plasma discharges of the Divertor Tokamak Test facility (DTT) in different
operational scenarios have been predicted by a comprehensive first-principle based …
operational scenarios have been predicted by a comprehensive first-principle based …
Development of compact tokamak fusion reactor use cases to inform future transport studies
The OMFIT STEP (Meneghini et al., Nucl. Fusion, vol. 10, 2020, p. 1088) workflow has been
used to develop inductive and steady-state H-mode core plasma scenario use cases for a …
used to develop inductive and steady-state H-mode core plasma scenario use cases for a …
Progress in extending high poloidal beta scenarios on DIII-D towards a steady-state fusion reactor and impact of energetic particles
J Huang, AM Garofalo, JP Qian, XZ Gong… - Nuclear …, 2020 - iopscience.iop.org
To prepare for steady-state operation of future fusion reactors (eg the International
Thermonuclear Experimental Reactor and China Fusion Engineering Test Reactor …
Thermonuclear Experimental Reactor and China Fusion Engineering Test Reactor …