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 …
Overview of the present progress and activities on the CFETR
Y Wan, J Li, Y Liu, X Wang, V Chan, C Chen… - Nuclear …, 2017 - iopscience.iop.org
Abstract The China Fusion Engineering Test Reactor (CFETR) is the next device in the
roadmap for the realization of fusion energy in China, which aims to bridge the gaps …
roadmap for the realization of fusion energy in China, which aims to bridge the gaps …
Progress of the CFETR design
G Zhuang, GQ Li, J Li, YX Wan, Y Liu, XL Wang… - Nuclear …, 2019 - iopscience.iop.org
Abstract The Chinese Fusion Engineering Testing Reactor (CFETR), complementing the
ITER facility, is aiming to demonstrate fusion energy production up to 200 MW initially and to …
ITER facility, is aiming to demonstrate fusion energy production up to 200 MW initially and to …
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 …
Present state of Chinese magnetic fusion development and future plans
J Li, Y Wan - Journal of Fusion Energy, 2019 - Springer
Chinese magnetic confinement fusion (MCF) development has made significant progress
during the past decade. With successful construction and operation of the EAST …
during the past decade. With successful construction and operation of the EAST …
Integrated modeling of CFETR hybrid scenario plasmas
J Chen, VS Chan, X Jian, X Zhang, Q Ren, G Li… - Nuclear …, 2021 - iopscience.iop.org
Demonstration of DEMO relevant fusion power (Pfus) level and tritium self-sufficiency are
two important goals of the China fusion engineering testing reactor (CFETR). In this work the …
two important goals of the China fusion engineering testing reactor (CFETR). In this work the …
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 …
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 …
Self-consistent modeling of CFETR baseline scenarios for steady-state operation
Integrated modeling for core plasma is performed to increase confidence in the proposed
baseline scenario in the 0D analysis for the China Fusion Engineering Test Reactor …
baseline scenario in the 0D analysis for the China Fusion Engineering Test Reactor …
Realization of minute-long steady-state H-mode discharges on EAST
G **anzu, WAN Baonian, LI Jiangang… - Plasma Science and …, 2017 - iopscience.iop.org
In the 2016 EAST experimental campaign, a steady-state long-pulse H-mode discharge with
an ITER-like tungsten divertor lasting longer than one minute has been obtained using only …
an ITER-like tungsten divertor lasting longer than one minute has been obtained using only …