Burn characteristics of compressed fuel pellets for D- sup 3 He inertial fusion
- Kyushu Univ., Dept. of Nuclear Engineering, Hakozaki, Fukuoka 812 (JP)
- Kyushu Univ., Dept. of Energy Conversion Engineering, Kasuga, Fukuoka 816 (JP)
In this paper, the feasibility of using D-{sup 3}He fuel in inertial confinement fusion is examined by using a hydrodynamics code that includes neutron and charged-particle transport routines. The use of a small amount of deuterium-tritium (D-T) ignitor is indispensable. Burn simulations are made for quasi-isobaric D-T/D-{sup 3}He pellet models compressed to 5000 times the liquid density. Substantial fuel gains ({approx}500) are obtained from pellets having parameters {rho}R{sub D-T} = 3 g/cm{sup 2} and {rho}R{sub total} = 14 g/cm{sup 2} and a central spark temperature of 5 keV. The amount of driver energy needed to achieve these gains is estimated to be {approx} 30 MJ when the coupling efficiency is 10%. The driver energy requirement can be reduced by using spin-polarized D-T and D-{sup 3}He fuels.
- OSTI ID:
- 7107437
- Journal Information:
- Fusion Technology; (United States), Journal Name: Fusion Technology; (United States) Vol. 22:1; ISSN 0748-1896; ISSN FUSTE
- Country of Publication:
- United States
- Language:
- English
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Related Subjects
700330 -- Plasma Kinetics
Transport
& Impurities-- (1992-)
700411* -- Inertial Confinement Devices-- (1992-)
BETA DECAY RADIOISOTOPES
BETA-MINUS DECAY RADIOISOTOPES
BURNUP
COMPRESSION
COMPUTER CODES
CONFINEMENT
DEUTERIUM
EVEN-ODD NUCLEI
FEASIBILITY STUDIES
FLUID MECHANICS
FUEL PELLETS
HELIUM 3
HELIUM ISOTOPES
HYDRODYNAMICS
HYDROGEN ISOTOPES
INERTIAL CONFINEMENT
ISOTOPES
LIGHT NUCLEI
MECHANICS
NEUTRAL-PARTICLE TRANSPORT
NEUTRON TRANSPORT
NUCLEI
ODD-EVEN NUCLEI
ODD-ODD NUCLEI
ORIENTATION
PELLETS
PLASMA CONFINEMENT
RADIATION TRANSPORT
RADIOISOTOPES
SIMULATION
SPIN ORIENTATION
STABLE ISOTOPES
TRITIUM
YEARS LIVING RADIOISOTOPES