Published 1994 | Version v1
Book

Some design aspects of D3He fuel inertial confinement fusion reactor

  • 1. Kyushu Univ., Fukuoka (Japan). Faculty of Engineering

Description

For a D3He fuel inertial confinement fusion (ICF) reactor, the efficiency of a direct energy recovery system using a capacitor load circuit is estimated to be as high as 70% by simulating the plasma behavior in a magnetic cavity. A three-dimensional (3-D) hybrid code is developed to analyze the instability on the surface of the expanding plasma in the magnetic field. We also performed burn simulations for a pure D3He target that adopts the volume ignition model as the final state of the implosion and found that it seems difficult to obtain the fuel gain required for the ICF reactor. (author)

Part of:
Emerging nuclear energy systems

Additional details

Publishing Information

Publisher
World Scientific Publishing Co. Pte. Ltd.
Imprint Place
Singapore (Singapore)
Imprint Title
Emerging nuclear energy systems
Imprint Pagination
576 p.
Journal Page Range
p. 71-75.

Conference

Title
7. international conference on emerging nuclear energy systems.
Acronym
ICENES'93
Dates
20-24 Sep 1993.
Place
Chiba (Japan).

Optional Information