Results 11 to 20 of about 2,976 (267)

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

Overview on the welding technologies of CLAM steel and the DFLL TBM fabrication

Nuclear Materials and Energy, 2016
Dual Functional Lithium Lead (DFLL) blanket was proposed for its advantages of high energy exchange efficiency and on-line tritium extraction, and it was selected as the candidate test blanket module (TBM) for China Fusion Engineering Test Reactor (CFETR)
Junyu Zhang, Bo Huang, Yutao Zhai, Shaojun Liu, Qingsheng Wu, Qunying Huang, F.D.S. Team   +6 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

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

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
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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

Parametric study of density wave instability in parallel channels of a water-cooled blanket in a fusion reactor

Frontiers in Energy Research, 2023
In fusion reactors, many blanket concepts are designed with water as a coolant to transfer high-density heat from the fusion reaction out of the reactor core.
Qiang Lian, Qiang Lian, Qiang Lian, Yu Liang, Haoyu Liao, Simiao Tang, Simiao Tang, Simiao Tang, Luteng Zhang, Luteng Zhang, Zaiyong Ma, Zaiyong Ma, Wan Sun, Wan Sun   +13 more
doaj   +1 more source

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

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   +1 more source

A Two-Way Neutronics/Thermal-Hydraulics Coupling Analysis Method for Fusion Blankets and Its Application to CFETR

Energies, 2020
The China Fusion Engineering Test Reactor (CFETR) is a tokamak device to validate and demonstrate fusion engineering technology. In CFETR, the breeding blanket is a vital important component that is closely related to the performance and safety of the ...
Tao Dai, Liangzhi Cao, Qingming He, Hongchun Wu, Wei Shen   +4 more
doaj   +1 more source

Nuclear Design of Heliotron Fusion Reactor Blankets

Journal of Nuclear Science and Technology, 1981
A study is made of the nuclear characteristics of blanket designs intended for a heliotron fusion reactor that employs an 1=2 helical heliotron field and no toroidal coils. The blankets in front of the superconducting magnet (shielding blankets) are utilized for neutron shielding, and the other blanket regions (breeding blankets) for tritium breeding ...
NAKASHIMA, Hideki, OHTA, Masao, ITOH, Hitoshi   +2 more
openaire   +1 more source