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Tritium content of a DT pellet in inertial confinement fusion

Published online by Cambridge University Press:  09 March 2009

Shigeo Kawata  and
Hideki Nakashima
Shigeo Kawata
Affiliation:
Department of Electrical Engineering, Nagaoka University ofTechnology, Nagaoka 940–21, Japan
Hideki Nakashima
Affiliation:
Department of Energy Conversion Engineering, Kyusyu University, Kasuga, Fukuoka 816, Japan
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Abstract

A numerical and analytical estimation and a one-dimensionalhydrodynamic simulation show that a 30%reduction of the tritium content in a D-T pellet still gives sufficient energy output in aD-T inertial confinement fusion reactor.In other words, the tritiumb content can be reduced significantly without a significant reduction in the D-T fusion energy output.This new result also meansthat the tritium inventory can be reduced significantly before and during the reactor operation in the D-T inertial confinement fusion.This result comes from the contribution of a D-D reaction to the D-T reaction.

Information

Type
Research Article
Information
Laser and Particle Beams , Volume 10 , Issue 3 , September 1992 , pp. 479 - 484
Copyright
Copyright © Cambridge University Press 1992

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