LIBRA–A light ion beam inertial confinement fusion reactor conceptual design

Cluster Ion Beam Polishing for Inertial Confinement Fusion Target Capsules

UWFDM-804 Activation Analysis for the LIBRA Light Ion Beam Fusion Conceptual Design

Activation calculations have been performed for the LIBRA reactor. Replacing HT-9 by low activation modified HT-9 increases the activity by a factor of 2.5 at shutdown while the long term activity drops by a factor of 25. The reflector is classified as Class C low level waste when modified HT-9 is used. Using HT-9 will require deep geological burial for the LIBRA radwaste. The activity produced...

Electron-Ion Temperature Relaxation Models for Inertial Confinement Fusion

Heavy ion driven reactor-size double shell inertial fusion targets

Inertial Confinement Fusion (ICF) is considered as an alternative to Magnetic Confinement Fusion to achieve controlled thermonuclear fusion. The main goal is to exploit the energy released from thermonuclear fusion reactions to produce electric energy. Heavy ion beams were proposed in 1976 as one of the possible drivers in ICF. The method consists in igniting few milligrams of deuterium-tritium...

Permeation fill-tube design for inertial confinement fusion target capsules

A unique approach for permeation filling of nonpermeable inertial confinement fusion target capsules with deuterium– tritium (DT) is presented. This process uses a permeable capsule coupled into the final target capsule with a 0.03-mmdiameter fill tube. Leak free permeation filling of glow-discharge polymerization (GDP) targets using this method have been successfully demonstrated, as well as i...