Results 181 to 190 of about 7,951 (222)

Tritium release from lithium titanate, a low-activation tritium breeding material

Journal of Nuclear Materials, 1994
Abstract The goals for fusion power are to produce energy in as safe, economical, and environmentally benign a manner as possible. To ensure environmentally sound operation low-activation materials should be used where feasible. The ARIES Tokamak Reactor Study has based reactor designs on the concept of using low-activation materials throughout the ...
J.P. Kopasz, J.M. Miller, C.E. Johnson
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Solid breeder blanket design and tritium breeding

Fusion Engineering and Design, 1991
Abstract Thermonuclear D–T power plants will have to be tritium self-sufficient. In addition to recovering the energy carried by the fusion neutrons (about 80% of the fusion energy), the blanket of the reactor will thus have to breed tritium to replace that burnt in the fusion process.
Proust, E., Anzidei, L., Dalle Donne, M., Fischer, U., Kuroda, T.   +4 more
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Aqueous tritium breeding blanket with natural lithium

Fusion Engineering and Design, 1989
An aqueous tritium breeding blanket concept with natural lithium has been proposed. Lithium oxide dissolved in pressurized heavy water forms a saturated solution of LiOD in the liquid phase and the remainder is suspended in the solution or forms a breeder solid skeleton.
Masabumi Nishikawa, Toshihiko Kawano, Kenzo Munakata, Yukinori Kanda, Hideki Nakashima   +4 more
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Tritium recovery from some ceramic breeding materials

Fusion Engineering and Design, 1989
Tritium retention measurements have been carried out on samples of LiAlO2, Li2SiO3 and Li2O of various density, irradiation time and temperature. The reported results were obtained by dissolution of the samples in concentrated KOH and by heating the samples up to 900 °C under a helium flow. Both techniques are described.
H. Kwast, A. Kout, R.P. Muis, M.P. Stijkel, A.J. Flipot, J.D. Elen   +5 more
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Tritium breeding control within liquid metal blankets

Fusion Engineering and Design, 2013
Abstract A key requirement for DEMO is the on-site breeding of tritium. In order to do this, a robust control system must be employed to ensure enough tritium is being bred to sustain the fusion reactor, whilst not breeding an amount which would exceed the plant's tritium inventory license.
L. Morgan, J. Pasley
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Lithium sol-gel ceramics for tritium breeding applications

Journal of Nuclear Materials, 1995
Abstract Tritium release experiments are performed on different lithium sol-gel ceramics showing identical microstructures. For γ-LiAlO2 type ceramics [Li4+xAl4−3xSi2xO8 (0:5 x:5 0.25)], the increase of the concentration of silicon atoms leads to a reduction of the temperature at which the tritium release curve reaches a maximum.
O. Renoult, J.-P. Boilot, J.-P. Korb, M. Boncoeur   +3 more
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Development of tritium dynamic transport analysis tool for tritium breeding blanket system using Modelica

Fusion Engineering and Design, 2020
Abstract Demonstration of the engineering feasibility of tritium breeding, including tritium generation, tritium extraction, tritium control and tritium safety is one of the main objectives of ITER Testing Blanket Module (TBM) Program. As one of TBM concepts, the tritium transport assessment of the China Helium Cooled Ceramic Breeder TBM and its ...
Ruyan Li, Xiaoyu Wang, Long Zhang, Jun Wang   +3 more
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An Assessment of Tritium Breeding Requirements Based on the Tritium Fuel Cycle

Fusion Technology, 1986
An assessment of tritium breeding requirements for fusion power reactors is presented. The analysis is based on an evaluation of time-dependent tritium inventories in the reactor system. The method presented can be applied to any fusion systems operating in a steady-state mode as well as in a pulsed mode.
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Experimental verification of tritium breeding performance of simulated aqueous slurries

The International Journal of Applied Radiation and Isotopes, 1985
An aqueous slurry of heavy water and lithium containing solids was examined to assess its merits as the tritium breeding, neutron attenuating, and heat removing portion of a first generation D-T fu...
Michael Schuller, Theodore A. Parish
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MECHANICAL PROPERTIES OF LiAl02 TRITIUM BREEDING CERAMICS

1991
Mechanical strength of porous LiAlO2 ceramic materials was investigated. Ultimate compressive strength and ultimate bending strength were measured both at room temperature and at 600°C. The room temperature results corroborate previous CEA ones. No decrease of mechanical strength at 600°C is observed.
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