Results 21 to 30 of about 506,342 (292)

Engineering Design of the European DEMO HCPB Breeding Blanket Breeder Zone Mockup

Applied Sciences, 2023
The Helium Cooled Pebble Bed (HCPB) breeding blanket is one of the two driver-blanket candidates for the European fusion demonstration power plant (EU DEMO) within the framework of the EUROfusion Consortium.
Guangming Zhou, Joerg Rey, Francisco A. Hernández, Ali Abou-Sena, Martin Lux, Frederik Arbeiter, Georg Schlindwein, Florian Schwab   +7 more
doaj   +1 more source

Design and simulation of a blanket module with high efficiency cooling system of tokamak focused on DEMO reactor

Nuclear Engineering and Technology, 2020
In this study, the neutronic calculation to obtain tritium breeding ratio (TBR) in a deuterium-tritium (D-T) fusion power reactor using Monte Carlo MCNPX is done. In addition, by using COMSOL software, an efficient cooling system is designed.
H. Sadeghi, R. Amrollahi, M. Zare, S. Fazelpour   +3 more
doaj   +1 more source

Conceptual design of solid-type Pb x Li y eutectic alloy breeding blanket for CFETR

Nuclear Fusion, 2023
As a key component of the Chinese Fusion Engineering and Test Reactor (CFETR), the blanket is responsible for tritium breeding, neutron shielding and energy conversion.
K. Jiang, Q. Wu, L. Chen, S. Liu
doaj   +1 more source

Instability of blanket bog slopes on Cuilcagh Mountain, N.W. Ireland [PDF]

There are many accounts of slope failures on blanket bogs, but their nature and controls are poorly understood. This study investigates the mechanisms of blanket bog failure on Cuilcagh Mountain, north-west Ireland, and identifies the critical factors ...
Kirk, Kathleen Jane
core   +3 more sources

Model Development and Transient Analysis of the HCPB BB BOP DEMO Configuration Using the Apros System Code

Energies, 2021
Extensive modeling and analytical work has been carried out considering the Helium-Cooled Pebble Bed Breeding Blanket (HCPB BB) Balance Of Plant (BOP) configuration of the Demonstration Power Plant (DEMO) using the Apros system code, developed by VTT ...
Marton Szogradi, Sixten Norrman
doaj   +1 more source

Modeling the Transport of Activated Corrosion Products in the WCLL PbLi Loop for ITER and the EU DEMO With the GETTHEM Code

IEEE Access, 2023
This work presents the results of the implementation in the GEneral Tokamak THErmal-hydraulic Model of available models for the generation and transport of any dispersed material in flowing PbLi eutectic mixture.
Fabrizio Lisanti, Pietro Arena, Roberto Bonifetto, Antonio Froio, Francisco Alberto Hernandez Gonzalez, Gandolfo Alessandro Spagnuolo, Roberto Zanino   +6 more
doaj   +1 more source

Activation analysis and waste management for dual functional lithium-lead blanket of the China Fusion Engineering Test Reactor

Fushe yanjiu yu fushe gongyi xuebao, 2021
Based on the design requirements of the first stage of the China Fusion Engineering Test Reactor (CFETR), the activation performance calculation and analysis of the components in the dual function lead-lithium blanket were performed using a neutron ...
ZENG Zhengkui, CHEN Size, YU Huiying, XIONG Houhua, DU Jifu, WANG Zhiwei   +5 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

An intelligent optimization method for the HCSB blanket based on an improved multi-objective NSGA-III algorithm and an adaptive BP neural network

Nuclear Engineering and Technology, 2023
To improve the performance of blanket: maximizing the tritium breeding rate (TBR) for tritium self-sufficiency, and minimizing the Dose of backplate for radiation protection, most previous studies are based on manual corrections to adjust the blanket ...
Wen Zhou, Guomin Sun, Shuichiro Miwa, Zihui Yang, Zhuang Li, Di Zhang, Jianye Wang   +6 more
doaj   +1 more source

Mechanical properties of several newly produced RAFM steels with Tungsten content in the range of 2 wt%

Nuclear Materials and Energy, 2020
The contribution of ENEA together with Rina-CSM to the Eurofusion programme “WPMAT-Advanced Seels” deals with the development of innovative RAFM steels able to withstand the critical temperatures typical of the different operational environments foreseen
C. Cristalli, L. Pilloni, O. Tassa, L. Bozzetto   +3 more
doaj   +1 more source