Results 31 to 40 of about 3,747 (225)

Advancement in tritium transport simulations for solid breeding blanket system [PDF]

Fusion Engineering and Design, 2016
Abstract In this paper, advancement on tritium transport simulations was demonstrated for a solid breeder blanket HCCR TBS, where multi-physics and detailed engineering descriptions are considered using a commercial simulation code. The physics involved includes compressible purge gas fluid flow, heat transfer, chemical reaction, isotope swamping ...
Ying, Alice, Zhang, Hongjie, Merrill, Brad J., Ahn, Mu-Young   +3 more
openaire   +1 more source

Neutronic analysis of a dual He/LiPb coolant breeding blanket for DEMO [PDF]

, 2010
A conceptual design of a DEMO fusion reactor is being developed under the Spanish Breeding Blanket Technology Programme: TECNO_FUS based on a He/LiPb dual coolant blanket as reference design option.
Aymar, Bloom, Cabellos, F. Ogando, Fischer, G. Veredas, I. Palermo, J. Sanz, J.M. Gómez-Ros, J.P. Catalán, L. Sedano, Norgett, Sanz, Tsuchiya, Watanabe, Wu   +15 more
core   +2 more sources

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

The Thorium Molten Salt Reactor : Moving on from the MSBR [PDF]

, 2005
A re-evaluation of the Molten Salt Breeder Reactor concept has revealed problems related to its safety and to the complexity of the reprocessing considered.
A. Nuttin, C. Garzenne, C. Le Brun, D. Heuer, D. Lecarpentier, E. Liatard, E. Merle-Lucotte, E. Walle, J. Wilson, J.-M. Loiseaux, L. Mathieu, Nuttin, O. Méplan, R. Brissot, Rosenthal   +14 more
core   +3 more sources

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

Converting energy from fusion into useful forms

, 2013
If fusion power reactors are to be feasible, it will still be necessary to convert the energy of the nuclear reaction into usable form. The heat produced will be removed from the reactor core by a primary coolant, which might be water, helium, molten ...
Harrington, C., Jenkins, I., Kiely, C., Kovari, M.   +3 more
core   +1 more source

Hybrid reactors: nuclear breeding or energy production? [PDF]

, 2010
After reviewing the long-standing tradition on hybrid research, an assessment model is presented in order to characterize the hybrid performance under different objectives. In hybrids, neutron multiplication in the subcritical blanket plays a major role,
Abánades Velasco, Alberto, Lafuente Mazuecos, Antonio, Martínez-Val Peñalosa, José María, Piera, Mireia   +3 more
core   +1 more source

Effect of Pebble Size Distribution and Wall Effect on Inner Packing Structure and Contact Force Distribution in Tritium Breeder Pebble Bed

Energies, 2021
In the tritium breeding blanket of nuclear fusion reactors, the heat transfer behavior and thermal-mechanical response of the tritium breeder pebble bed are affected by the inner packing structure, which is crucial for the design and optimization of a ...
Baoping Gong, Hao Cheng, Yongjin Feng, Xiaofang Luo, Long Wang, Xiaoyu Wang   +5 more
doaj   +1 more source

Conceptual design of the enhanced coolant purification systems for the European HCLL and HCPB test blanket modules [PDF]

, 2019
The Coolant Purification Systems (CPSs) is one of the most relevant ancillary systems of European Helium Cooled Lead Lithium (HCLL) and Helium Cooled Pebble Bed (HCPB) Test Blanket Modules (TBMs) which are currently in the preliminary design phase in ...
Aiello A., Arena P., Di Maio P. A., Ferrucci B., Forte R., Galabert J., Granieri M., Ortiz C., Ricapito I., Tincani A., Voukelatou K.   +10 more
core   +1 more source

Diagnostic systems in DEMO: engineering design issues

, 2014
The diagnostic systems of DEMO that are mounted on or near the torus, whether intended for the monitoring and control functions of the engineering aspects or the physics behaviour of the machine, will have to be designed to suit the hostile nuclear ...
Todd, T N
core   +1 more source