Neutron transport in burning D-T pellets for inertial confinement fusion

Conference · Wed Oct 05 00:00:00 EDT 1994 · AIP Conference Proceedings (American Institute of Physics); (United States)

OSTI ID:6836027

Nakashima, H ^[1]; Nakao, Y; Oda, A; Kudo, K ^[2]

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1. Department of Energy Conversion Engineering, Kyushu University, Kasuga, Fukuoka 816 (Japan)
2. Department of Nuclear Engineering, Kyushu University, Hakozaki, Fukuoka 812 (Japan)

On the basis of coupled transport-hydrodynamic calculations, we investigate the effect of neutron heating on the burn dynamics of ICF pellets. We also evaluate the energy spectrum of neutrons emitted out of a typical burning pellet. Because of rapid pellet expansion, these neutrons contain fast components with energies of more than 20 MeV. Tritium breeding ratio (TBR) is estimated using the realistic neuron energy spectrum for typical D-T laser fusion reactors. It is found that the TBR obtained is smaller by about 5--15% as compared to the case of 14-MeV monochromatic source. [copyright] 1994 [ital American] [ital Institute] [ital of] [ital Physics]

• OSTI ID: 6836027
• Report Number(s): CONF-931048-; CODEN: APCPCS; TRN: 95-004122
• Journal Information: AIP Conference Proceedings (American Institute of Physics); (United States), Vol. 318:1; Conference: 11. international workshop on laser interaction and related plasma phenomena, Monterey, CA (United States), 25-29 Oct 1993; ISSN 0094-243X
• Country of Publication: United States
• Language: English

Related Subjects

70 PLASMA PHYSICS AND FUSION TECHNOLOGY
D-T REACTORS
LASER TARGETS
NEUTRON TRANSPORT
DEUTERIUM TARGET
EXPANSION
FUEL PELLETS
INERTIAL CONFINEMENT
NEUTRON SPECTRA
TRITIUM TARGET
CONFINEMENT
NEUTRAL-PARTICLE TRANSPORT
PELLETS
PLASMA CONFINEMENT
RADIATION TRANSPORT
SPECTRA
TARGETS
THERMONUCLEAR REACTORS
700411* - Inertial Confinement Devices- (1992-)