Results 11 to 20 of about 9,751 (308)

Defects, dopants and Li-ion diffusion in Li2SiO3 [PDF]

, 2014
Запропонована логіко-структурна схема концепції управління інвестиційним забезпеченням промислового підприємства, яка враховує положення підприємства в зовнішньому та внутрішньому середовищах та підвищення ефективності його функціонування.
Kuganathan, N., Tsoukalas, L.H., Chroneos, A.   +2 more
core   +4 more sources

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

Corrosion characteristics of reduced activation ferritic-martensitic steel EUROFER by Li2TiO3 with excess Li

Nuclear Materials and Energy, 2018
In a solid breeding blanket, ceramic breeder pebbles are in contact with reduced activation ferritic martensitic (RAFM) steel at high temperatures for years and accordingly form a corrosion layer on the blanket structural steel.
Keisuke Mukai, Fernando Sanchez, Tsuyoshi Hoshino, Regina Knitter   +3 more
doaj   +1 more source

Parametric thermal analysis for the optimization of Double Walled Tubes layout in the Water Cooled Lithium Lead inboard blanket of DEMO fusion reactor [PDF]

, 2019
Within the roadmap that will lead to the nuclear fusion exploitation for electric energy generation, the construction of a DEMOnstration (DEMO) reactor is, probably, the most important milestone to be reached since it will demonstrate the technological ...
Arena P., Del Nevo A., Di Maio P. A., Forte R., Nevone G.   +4 more
core   +1 more source

A Two-Way Neutronics/Thermal-Hydraulics Coupling Analysis Method for Fusion Blankets and Its Application to CFETR

Energies, 2020
The China Fusion Engineering Test Reactor (CFETR) is a tokamak device to validate and demonstrate fusion engineering technology. In CFETR, the breeding blanket is a vital important component that is closely related to the performance and safety of the ...
Tao Dai, Liangzhi Cao, Qingming He, Hongchun Wu, Wei Shen   +4 more
doaj   +1 more source

IFMIF suitability for evaluation of fusion functional materials [PDF]

, 2011
The International FusionMaterials Irradiation Facility (IFMIF) is a future neutron source based on the D-Li stripping reaction, planned to test candidate fusionmaterials at relevant fusion irradiation conditions.
A. García, A. Ibarra, Arnold, Casal, D. Rapisarda, Daum, Decreton, F. Mota, F. Sordo, Fischer, Grant, Hodgson, J. Jordanova, M. Perlado, Malang, Malang, Malerba, Moeslang, Mota, N. Casal, R. Vila, Simakov, Simakov, V. Queral, Vladimirov, Wachtman   +25 more
core   +2 more sources

Considering for the blanket structure scheme of HCCB DEMO

Theoretical and Applied Mechanics Letters, 2019
: For the solid blanket concept of helium cooled ceramic breeder (HCCB) demonstration fusion power plant (DEMO), a feasible blanket structure with configuration 2×X is proposed as considering relatively low temperature limit of neutron multiplier ...
Zhou Zhao, Zaixin Li, Xiaoyu Wang, Xueren Wang, Kaiming Feng   +4 more
doaj   +1 more source

U.S. Solid Breeder Blanket Design for ITER [PDF]

Fusion Technology, 1991
The US blanket design activity has focused on the developments and the analyses of a solid breeder blanket concept for ITER. The main function of this blanket is to produce the necessary tritium required for the ITER operation and the test program. Safety, power reactor relevance, low tritium inventory, and design flexibility are the main reasons for ...
Y. Gohar, H. Attaya, M. Billone, C. Lin, C. Johnson, S. Majumdar, D. Smith, A. Raffray, A. Badawi, Z. Gorbis, A. Ying, M. Abdou, P. Goranson, B. Nelson, D. Williamson, C. Baker, I. Sviatoslavsky, J. Blanchard, E. Mogahed, M. Sawan, G. Kulcinski   +20 more
openaire   +1 more source

Three-dimensional thermal-hydraulics/neutronics coupling analysis on the full-scale module of helium-cooled tritium-breeding blanket

Nuclear Engineering and Technology, 2023
Blanket is of vital importance for engineering application of the fusion reactor. Nuclear heat deposition in materials is the main heat source in blanket structure.
Qiang Lian, Simiao Tang, Longxiang Zhu, Luteng Zhang, Wan Sun, Shanshan Bu, Liangming Pan, Wenxi Tian, Suizheng Qiu, G.H. Su, Xinghua Wu, Xiaoyu Wang   +11 more
doaj   +1 more source

DEMO WCLL BB breeding zone cooling system design: analysis and discussion [PDF]

, 2019
The Water-Cooled Lithium-Lead (WCLL) Breeding Blanket (BB) is a key component in charge of ensuring Tritium self-sufficiency, shielding the Vacuum Vessel and removing the heat generated in the tokamak plasma.
Caruso, Gianfranco, Del Nevo, Alessandro, Edemetti, Francesco, Martelli, Emanuela, Tassone, Alessandro   +4 more
core   +1 more source