Results 81 to 90 of about 525,516 (210)
BABY 1L: first tritium breeding campaign results
Nuclear FusionAchieving tritium self-sufficiency is a critical challenge for future fusion power plants. The BABY 1 L experiment, part of the LIBRA project at MIT, aims to benchmark tritium breeding and release in molten salt breeder systems under deuterium–tritium ...
Rémi Delaporte-Mathurin +10 more
doaj +1 more source
Minimum-thickness blanket/shield with optimum tritium breeding and shielding effectiveness [PDF]
, 1978 A blanket/shield assembly for a fusion reactor has been designed through extensive optimization studies. The design was optimized under the following constraints: (a) minimum overall thickness, (b) tritium breeding ratio of 1.10, (c) thermal energy ...
Gerstl, S.A.W.
core
Tokamak fusion reactors with less than full tritium breeding
, 1983 A study of commercial, tokamak fusion reactors with tritium concentrations and tritium breeding ratios ranging from full deuterium-tritium operation to operation with no tritium breeding is presented.
Evans, K., Jr., Gilligan, J.G., Jung, J.
core +1 more source
Fissile core and Tritium-Breeding Blanket: structural materials and their requirements
Comptes Rendus. Physique, 2008 High radiation resistant structural materials for fusion and fission nuclear power plants are a key issue for the development of both types of reactors. Selection criteria, elements of metallurgy of the selected materials, and the major issues as they are revealed by the results of the present development programmes, are presented.
Jean-Louis Boutard +3 more
openaire +1 more source
Nuclear FusionStellarator reactor design and optimization requires quick and accurate neutronic simulations for obtaining tritium breeding ratio, coil neutron flux, and volumetric neutron heating.
Timo J. Bogaarts, Felix Warmer
doaj +1 more source
Accident-tolerant hybrid ceramics for fusion breeding blanket
Materials & DesignIn a water-cooled ceramic breeding blanket for fusion reactors, hydrogen gas generation by steam oxidation of metallic Be compounds (i.e. neutron multiplier) in a loss-of-coolant accident (LOCA) raises major safety concerns.
Keisuke Mukai +3 more
doaj +1 more source
Research on Neutronics/Thermal-hydraulics Coupling Effect of CFETR Blanket
Yuanzineng kexue jishu, 2022 Chinese Fusion Engineering Test Reactor (CFETR) has been proposed to bridge the technology gap between the International Thermonuclear Experimental Reactor (ITER) and the Fusion Demonstration Reactor (DEMO). As the most crucial nuclear component, fusion
DAI Tao;CAO Liangzhi;HE Qingming;WU Hongchun
doaj
Tritium management in HCLL-PPCS Model AB blanket
, 2007 When dealing with activities related to the design and optimisation of the Helium Cooled Lithium Lead (HCLL) blanket, doubts arose in the past about the technical feasibility of the tritium processing system. The questionable feasibility was due to the
M. UTILI +5 more
core +1 more source
ITER Water Cooled Lithium Lead Test Blanket System transient thermal-hydraulic analysis
Nuclear FusionThe planned experimental activities of the ITER Test Blanket Module (TBM) program will be a key step in understanding the physics and technologies required for tritium breeding blankets, which are essential for achieving tritium self-sufficiency in a ...
Tommaso Glingler +9 more
doaj +1 more source
Advancing tritium self-sufficiency in fusion power plants: insights from the BABY experiment
Nuclear FusionIn the pursuit of fusion power, achieving tritium self-sufficiency stands as a pivotal challenge. Tritium breeding within molten salts is a critical aspect of next-generation fusion reactors, yet experimental measurements of Tritium Breeding Ratio (TBR ...
Rémi Delaporte-Mathurin +15 more
doaj +1 more source