Results 11 to 20 of about 1,114 (183)

Study on Multiphysics Coupling and Automatic Neutronic Optimization for Solid Tritium Breeding Blanket of Fusion Reactor

Energies, 2021
A tritium breeding blanket (TBB) is an essential component in a fusion reactor, which has functions of tritium breeding, energy generation and neutron shielding.
Shen Qu, Qixiang Cao, Xuru Duan, Xueren Wang, Xiaoyu Wang   +4 more
doaj   +1 more source

Effect of annealing on microstructure and thermal conductivity of Li2TiO3 and Li4SiO4

Nuclear Materials and Energy, 2022
Li2TiO3 and Li4SiO4 are considered as candidate tritium breeding materials due to its excellent physical, chemical and tritium release performance. Thermal conductivities of solid tritium breeding materials are determined by microstructure, sintering ...
Baolong Ji, Chi Wang, Shouxi Gu, Qiang Qi, Yingchun Zhang, Haishan Zhou, Guang-Nan Luo   +6 more
doaj   +1 more source

Multiphysics Optimization for First Wall Design Enhancement in Water-Cooled Breeding Blankets

Nuclear Materials and Energy, 2021
The commercial feasibility of the first fusion power plant generation adopting D-T plasma is strongly dependent upon the self-sustainability in terms of tritium fuelling. Within such a kind of reactor, the component selected to house the tritium breeding
Ruggero Forte, Pierluigi Chiovaro, Pietro Alessandro Di Maio, Nasr Ghoniem   +3 more
doaj   +1 more source

HCCR breeding blankets optimization by changing neutronic constrictions

Nuclear Engineering and Technology, 2021
The neutronic analysis of Helium Cooled Ceramic Reflector (HCCR) breeding blankets has been performed using the 3D Monte Carlo code MCNPX and ENDF nuclear data library.
R. Zadfathollah Seighalani, M. Sedaghatizade, H. Sadeghi   +2 more
doaj   +1 more source

Impact of blanket material and configuration on the size of a tokamak fusion reactor

Nuclear Materials and Energy, 2021
On the basis of the Korean fusion roadmap, conceptual design of the DEMO and R&D on the breeding blanket are ongoing. This article addresses the impact of blanket material and configuration on the tritium breeding, shielding characteristics, and ...
Bong Guen Hong
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

Overview of the ITER TBM program

He jishu, 2022
The tritium breeding blanket (TBB) technology is one of the key technologies to be solved and also one of three major issues in the development of fusion reactor in the future. The international thermonuclear experimental reactor (ITER) will be the first
SHENG Qian, WU Shuqin, WANG Xiaoyu, ZHAO Fengchao, LUO Xiaofang, QIAN Xiaoyong, LUO Delong   +6 more
doaj   +1 more source

Optimal Radial Build and Transmutation Properties of a Fusion-Based Transmutation Reactor with Molten Salt Coolants

Energies, 2022
The optimal shape of a fusion-based transmutation reactor with a molten salt coolant was determined by plasma physics, technology, and neutronic requirements.
Bong-Guen Hong
doaj   +1 more source

Analysis of Coolant Purification Strategies for Tritium Control in DEMO Water Primary Coolant

Energies, 2023
A major objective of the European fusion program is the design of the DEMOnstration power plant named DEMO. Up to now, most fusion experiments have been dedicated to a plasma physics investigation while, in DEMO-oriented activities, large attention is ...
Vincenzo Narcisi, Andrea Quartararo, Ivo Moscato, Alessia Santucci   +3 more
doaj   +1 more source

The European DEMO Helium Cooled Pebble Bed Breeding Blanket: Design Status at the Conclusion of the Pre-Concept Design Phase

Energies, 2023
Significant design efforts were undertaken during the Pre-Concept Design (PCD) phase of the European DEMO program to optimize the helium cooled pebble bed (HCPB) breeding blanket.
Guangming Zhou, Francisco A. Hernández, Pavel Pereslavtsev, Béla Kiss, Anoop Retheesh, Luis Maqueda, Jin Hun Park   +6 more
doaj   +1 more source