Results 181 to 190 of about 525,516 (210)
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Electronic Measurement of Tritium Breeding in a Fusion Blanket Assembly

Fusion Technology, 1989
The tritium production rate (TPR) distribution in a fusion blanket assembly previously determined from measurements of tritium beta activity was remeasured using an independent electronic method. The results agreed within the experimental errors and confirmed the previously reported discrepancies with predictions based on three-dimensional Monte Carlo ...
openaire   +1 more source

Effect of Blanket Structure on Tritium Breeding Ratio in Fusion Reactors

Nuclear Technology - Fusion, 1983
Effects of blanket composition, including materials and their thicknesses, on the tritium breeding ratio in tokamak fusion reactors are investigated for the Li/sub 2/O blanket having a separable first wall. The sensitivities of the breeding ratio to the thicknesses of the materials for the first wall are estimated as follows (unit: T /SUB BR/ /cm): S ...
Koichi Maki, Takashi Okazaki
openaire   +1 more source

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   +3 more
openaire   +1 more source

Models of Ceramic Tritium Breeding Zones in the Blanket of a Thermonuclear Reactor

Atomic Energy, 2000
The development, performed in the 1980s–1990s, of models of tritium breeding zones for blankets of thermonuclear reactors, based on the use of ceramic lithium-containing materials, is described. 5 figures, 1 table.
V. A. Gorokhov   +14 more
openaire   +1 more source

Thermal-hydraulic and thermo-structural analyses of the STARFIRE/DEMO tritium-breeding blanket

Nuclear Engineering and Design. Fusion, 1984
Abstract Design features and thermal-hydraulic and thermo-structural aspects of the STARFIRE/DEMO tritium-breeding blankets are described and discussed. Design calculations which take into account thermal, mechanical, and materials performance, indicate favorable results for the viability of the blanket designs in general and point to key issues ...
Y LIU   +4 more
openaire   +1 more source

TRITIUM BREEDING SELF-SUFFICIENCY OF DEMO REACTORS WITH A WATER-COOLED PB17LI BLANKET

1993
In the frame of the studies developed for DEMO breeding blankets, a type of blanket with Pb17Li as breeder and water as coolant has been developed at the JRC-Ispra. It deals with breeder circular modules, internally cooled by water in U-type tubes and arranged poloidally according to rows inside boxes, named segments.
Casini, G.   +3 more
openaire   +2 more sources

AN ELECTRICITY PRODUCING AND TRITIUM BREEDING BLANKET SECTOR FOR INTOR

1983
A Bond   +5 more
openaire   +1 more source

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