Results 41 to 50 of about 495 (172)

Calculation of Radioactivity and Dose Rate of Activated Corrosion Products in Water‐Cooled Fusion Reactor

open access: yesScience and Technology of Nuclear Installations, Volume 2016, Issue 1, 2016., 2016
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

Experimental Verification of Tritium Production Rate in CFETR Water Cooled Ceramic Breeder Blanket Mock up

open access: yesYuanzineng kexue jishu, 2022
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

open access: yes, 2021
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

Preliminary CFD and EM analysis of the ECRH equatorial launcher port plug prototype towards the CFETR

open access: yesNuclear Materials and Energy, 2023
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

Parameter Identification of Heavy-Duty Manipulator Using Stochastic Gradient Hamilton Monte Carlo Method

open access: yesIEEE Access, 2023
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

open access: yes, 2019
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]

open access: yes, 2015
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

open access: yesEnergies, 2021
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

open access: yes, 2018
AC loss measurement date and characteristics of joint for CFETR ...
yi, S
core   +2 more sources

Home - About - Disclaimer - Privacy