Results 41 to 50 of about 495 (172)
In water‐cooled reactor, the dominant radioactive source term under normal operation is activated corrosion products (ACPs), which have an important impact on reactor inspection and maintenance. A three‐node transport model of ACPs was introduced into the new version of ACPs source term code CATE in this paper, which makes CATE capable of theoretically
Jingyu Zhang +4 more
wiley +1 more source
As one of CFETR’s candidate blankets, water cooled ceramic breeder (WCCB) blanket undertakes important nuclear-related functions such as tritium breeding, nuclear heat extraction, and neutron shielding.
ZHU Qingjun;CHEN Wuhui;BAO Jie;ZHAO Zijia;DU Hua;HUANG Kai;LIU Songlin
doaj
Scoping study of lower hybrid current drive for CFETR
Submitted for publication in Nuclear FusionThe paper assesses the applicability of lower hybrid current drive (LHCD) for two potential operating scenarios for the China Fusion Engineering Test Reactor (CFETR): the “hybrid” scenario in which some of the ...
Chen, J. +8 more
core +1 more source
The CFETR is the next generation magnetic confinement tokamak, its increasing heating needs and stringent shielding requirements present new challenges for the ECRH launcher.
Dingzhen Li +8 more
doaj +1 more source
This study focuses on the parameter identification of a heavy-duty manipulator used in the remote maintenance of the China Fusion Engineering Test Reactor (CFETR).
Qi Wang +5 more
doaj +1 more source
Data for: The Impacts of Blanket on CFETR Ohmic Breakdown
These are data from the calculations of the impacts of blanket on CFETR ohmic breakdown. Some of the input data are assumed for the purpose of evaluating the impacts of blanket on ohmic breakdown, and the other input data are from the engineering designs
Ye, M (via Mendeley Data)
core +1 more source
Optimization of CFETR CSMC cabling based on numerical modeling and experiments [PDF]
The China Fusion Engineering Test Reactor (CFETR) is a new tokamak device, whose magnet system includes toroidal field (TF), central solenoid (CS) and poloidal field (PF) coils.
Liu, Bo +10 more
core +1 more source
Thermal Hydraulic Analysis on the Water Lead Lithium Cooled Blanket for CFETR
A new type of Water Lead Lithium Cooled (WLLC) blanket that adopts the modular design scheme, water cooling the structure components, liquid PbLi as breeder and coolant, and SiC as the thermal insulator between PbLi and structures is under development as
Kecheng Jiang +6 more
doaj +1 more source
Data for: AC Loss Test and Analysis of the Prototype CIC Conductor Joint for CFETR CSMC
AC loss measurement date and characteristics of joint for CFETR ...
yi, S
core +2 more sources

