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)
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).
INIS
- Country of Publication
- Singapore
- Country of Input or Organization
- Japan
- INIS RN
- 26027744
- Subject category
- S70: PLASMA PHYSICS AND FUSION TECHNOLOGY;
- Resource subtype / Literary indicator
- Conference
- Descriptors DEI
- DEUTERIUM; DIRECT ENERGY CONVERSION; ENERGY RECOVERY; HELIUM 3; INERTIAL CONFINEMENT; LASER FUSION REACTORS; PLASMA EXPANSION; RAYLEIGH-TAYLOR INSTABILITY; SPECIFICATIONS; THERMONUCLEAR IGNITION
- Descriptors DEC
- CONFINEMENT; CONVERSION; ENERGY CONVERSION; EVEN-ODD NUCLEI; EXPANSION; HELIUM ISOTOPES; HYDROGEN ISOTOPES; INSTABILITY; ISOTOPES; LIGHT NUCLEI; NUCLEI; ODD-ODD NUCLEI; PLASMA CONFINEMENT; STABLE ISOTOPES; THERMONUCLEAR REACTORS