Results 11 to 20 of about 967,607 (110)

Impact of Blanket Configuration on the Design of a Fusion-Driven Transmutation Reactor [PDF]

International Journal of Renewable Energy Development, 2018
A configuration of a fusion-driven transmutation reactor with a low aspect ratio tokamak-type neutron source was determined in a self-consistent manner by using coupled analysis of tokamak systems and neutron transport.
Bong Guen Hong
doaj   +4 more sources

Considering for the blanket structure scheme of HCCB DEMO

Theoretical and Applied Mechanics Letters, 2019
: For the solid blanket concept of helium cooled ceramic breeder (HCCB) demonstration fusion power plant (DEMO), a feasible blanket structure with configuration 2×X is proposed as considering relatively low temperature limit of neutron multiplier ...
Zhou Zhao, Zaixin Li, Xiaoyu Wang, Xueren Wang, Kaiming Feng   +4 more
doaj   +2 more sources

NITA Coil—Innovation for Enlarging the Blanket Space in the Helical Fusion Reactor [PDF]

, 2016
0000-0002-4489-8241An innovative idea is proposed for enlarging the blanket space on the inboard side of the torus for the helical fusion reactor FFHR-d1.
Akio SAGARA, Nagato YANAGI, Junichi MIYAZAWA, MIYAMZAWA, Junichic, Takuya GOTO, Hitoshi TAMURA, YANAGI, Nagato, TAMURA, Hitoshi, GOTO, Takuya, SAGARA, Akio   +9 more
core   +2 more sources

Neutronics analysis of thorium-uranium based molten salt blanket in stellarator-type FFHR

, 2021
The stellarator-type Fusion-Fission Hybrid Reactor (FFHR) is an alternative conceptual design for the tokamak-based devices in order to realize the stable power output.
Gu, Long (author), Zhang, You-Peng (author), Yao, Cun-Feng (author), Li, Jin-Yang (author), Zhang, Lu (author), Xu, Hu-Shan (author), Yu, Rui (author), Dai, Yong (author), Jiang, Wei (author)   +8 more
core   +1 more source

Study on the effect of neutron shielding design on tritium breeding based on water-cooled ceramic blanket for CFETR

AIP Advances, 2023
The Chinese Fusion Engineering Test Reactor (CFETR) is a magnetic confinement fusion reactor independently designed and developed by China, which is based on the ITER design experience.
Jie Li, Hang Li, Muquan Wu, Xiang Zhu, Peiguang Yan, Xiaodong Lin, Jie Zhang, Xiang Gao   +7 more
doaj   +1 more source

Progress on design and related R&D activities for the water-cooled breeder blanket for CFETR

Theoretical and Applied Mechanics Letters, 2019
: The water-cooled ceramic breeder (WCCB) blanket is one of the blanket candidates for Chinese fusion engineering testing reactor (CFETR) and is being developed at the Institute of Plasma Physics, Chinese Academy of Sciences (ASIPP).
Songlin Liu, Xiaoman Cheng, Xuebin Ma, Lei Chen, Kecheng Jiang, Xia Li, Hui Bao, Jichao Wang, Wanjing Wang, Changhong Peng, Peng Lu, Min Li, Kai Huang   +12 more
doaj   +1 more source

A coupled systems code - CMHD solver for fusion blanket design [PDF]

, 2016
Fusion blankets are required to operate in a harsh environment under the influence of a number of synergistic physical phenomena, working across several length scales.
Wolfendale, Michael
core   +1 more source

Utilization of fusion neutrons in the tokamak fusion test reactor for blanket performance testing and other nuclear engineering experiments [PDF]

, 1979
In addition to developing a set of reacting-plasma/blanket-neutronics benchmark data, the TFTR fusion application experiments would provide operational experience with fast-neutron dosimetry and the remote handling of blanket modules in a tokamak reactor
Caldwell, C. S., Pettus, W. G., Womack, R., Schmotzer, J. K., C.S. Caldwell, R. Womack, Welfare, F., W.G. Pettus, F. Welfare, J.K. Schmotzer   +9 more
core   +1 more source

Three-dimensional thermal-hydraulics/neutronics coupling analysis on the full-scale module of helium-cooled tritium-breeding blanket

Nuclear Engineering and Technology, 2023
Blanket is of vital importance for engineering application of the fusion reactor. Nuclear heat deposition in materials is the main heat source in blanket structure.
Qiang Lian, Simiao Tang, Longxiang Zhu, Luteng Zhang, Wan Sun, Shanshan Bu, Liangming Pan, Wenxi Tian, Suizheng Qiu, G.H. Su, Xinghua Wu, Xiaoyu Wang   +11 more
doaj   +1 more source

The impact of design parameters on tritium breeding in a water cooled blanket for CFETR [PDF]

AIP Advances
The CFETR (China Fusion Engineering Test Reactor) is a major Chinese scientific project to design, build, and operate a next-generation tokamak nuclear fusion reactor.
Jie Li, Haiyan Yang, Jie Zhang
doaj   +1 more source