Results 1 to 10 of about 297 (183)

Tritium transport model at breeder unit level for HCLL breeding blanket

Fusion Engineering and Design, 2019
Abstract The Helium-Cooled Lithium Lead (HCLL) breeding blanket is one of the European blanket designs proposed for DEMO reactor. A tritium transport model is fundamental for the correct assessment of both design and safety, in order to guarantee tritium self-sufficiency and to characterize tritium concentrations, inventories and losses.
Luigi Candido, Marco Utili, Raffaella Testoni   +2 more
exaly   +4 more sources

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

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

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

Tritium Breeding Blanket [PDF]

Fusion Technology, 1991
The terms of reference for ITER provide for incorporation of a tritium breeding blanket with a breeding ratio as close to unity as practical. A breeding blanket is required to assure an adequate supply of tritium to meet the program objectives. Based on specified design criteria, a ceramic breeder concept with water coolant and an austenitic steel ...
D. Smith, M. Billone, Y. Gohar, A. Raffray, W. Daenner, D. Lorenzetto, C. Baker, I. Sviatoslavsky, A. Anitipenkov, A. Siderov, S. Mori, T. Kuroda, K. Maki, H. Takatsu, H. Yoshida, G. Simbolotti, G. Shatalov   +16 more
openaire   +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

Neutronic analysis of effects of inboard materials on the size of a tokamak fusion reactor

Nuclear Materials and Energy, 2021
The effects of inboard materials on the size of a tokamak fusion reactor were studied based on reactor system parameters determined through a coupled analysis of tokamak systems and neutron transport. With an inboard blanket, the shielding capability was
B.G. Hong, W. Cho
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

Neutronic Activity for Development of the Promising Alternative Water-Cooled DEMO Concepts

Applied Sciences, 2023
An emerging breeding blanket that fulfills performance criteria, meets the safety requirements, and is reliable enough to meet the plant availability is a challenging issue that assumes complex studies involving numerous neutronic analyses based on the ...
Pavel Pereslavtsev, Francisco Alberto Hernández, Ivo Moscato, Jin Hun Park   +3 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