A review of radiative detachment studies in tokamak advanced magnetic divertor configurations
VA Soukhanovskii - Plasma Physics and Controlled Fusion, 2017 - iopscience.iop.org
The present vision for a plasma–material interface in the tokamak is an axisymmetric
poloidal magnetic X-point divertor. Four tasks are accomplished by the standard poloidal X …
poloidal magnetic X-point divertor. Four tasks are accomplished by the standard poloidal X …
Physics design of new lower tungsten divertor for long-pulse high-power operations in EAST
A new lower tungsten divertor has been developed and installed in the EAST
superconducting tokamak to replace the previous graphite divertor with power handling …
superconducting tokamak to replace the previous graphite divertor with power handling …
[HTML][HTML] Recent progress of plasma exhaust concepts and divertor designs for tokamak DEMO reactors
The power exhaust concept and an appropriate divertor design are common critical issues
for tokamak DEMO design activities which have been carried out in Europe, Japan, China …
for tokamak DEMO design activities which have been carried out in Europe, Japan, China …
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 …
Studies of power exhaust and divertor design for a 1.5 GW-level fusion power DEMO
N Asakura, K Hoshino, S Suzuki, S Tokunaga… - Nuclear …, 2017 - iopscience.iop.org
Power exhaust to the divertor and the conceptual design have been investigated for a
steady-state DEMO in Japan with 1.5 GW-level fusion power and the major radius of 8.5 m …
steady-state DEMO in Japan with 1.5 GW-level fusion power and the major radius of 8.5 m …
Non-contact measurement of thermal diffusivity in ion-implanted nuclear materials
Abstract Knowledge of mechanical and physical property evolution due to irradiation
damage is essential for the development of future fission and fusion reactors. Ion-irradiation …
damage is essential for the development of future fission and fusion reactors. Ion-irradiation …
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 …
Present status of liquid metal research for a fusion reactor
FL Tabarés - Plasma Physics and Controlled Fusion, 2015 - iopscience.iop.org
Although the use of solid materials as targets of divertor plasmas in magnetic fusion
research is accepted as the standard solution for the very challenging issue of power and …
research is accepted as the standard solution for the very challenging issue of power and …
Thermal conductivity reduction of tungsten plasma facing material due to helium plasma irradiation in PISCES using the improved 3-omega method
The near-surface region of plasma facing material (PFM) plays an important role in thermal
management of fusion reactors. In this work, we measured thermal conductivity of tungsten …
management of fusion reactors. In this work, we measured thermal conductivity of tungsten …