Pressure and impulse scaling methods for wall impact in ICF (inertial confinement fusion)

Conference · Mon Jan 01 00:00:00 EST 1990

OSTI ID:6598114

Liu, J C; Chen, X M; Schrock, V E ^[1]; Orth, C D ^[2]

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1. California Univ., Berkeley, CA (USA). Dept. of Nuclear Engineering
2. Lawrence Livermore National Lab., CA (USA)

The design of the first structural wall (FSW) in an inertial confinement fusion (ICF) reactor requires some knowledge of the expected wall loading produced by x-ray and neutron deposition; specifically in the High Yield Lithium Injection Fusion Energy (HYLIFE) reactor, wall loading results from two sources -- gas shock and liquid impact. Gas shock is derived from x-ray deposition in the thin layers of exposed blanket material, producing ionized vapor, which will generate gas shock on the FSW. Liquid impact, on the other hand, results from the acceleration of liquid blanket material by two possible forces -- the drag from vapor expansion through the blanket material and the neutron-induced isochoric disassembly process. Both impacts, however, are coupled by the interaction of hot gas expanding through the liquid blanket. This paper discusses scaling methods for estimating pressure and impulse on the HYLIFE FSW from these impacts. In particular, this paper reviews simple analytical and numerical techniques, and the use of experimental results in the estimation of wall impacts for the HYLIFE blanket geometry. Considered important in the analyses are supersonic flow through jet arrays and isochoric disassembly. Given the same initial parameters as those used in previous HYLIFE studies, the techniques described here yield results comparable to the previous studies utilizing heavy numerical simulation.

• Research Organization: Lawrence Livermore National Lab., CA (USA)
• Sponsoring Organization: DOE/DP
• DOE Contract Number: W-7405-ENG-48
• OSTI ID: 6598114
• Report Number(s): UCRL-CR-103910; CONF-901007-14; ON: DE91000949
• Resource Relation: Conference: 9. topical meeting on technology of fusion energy, Oak Brook, IL (USA), 7-11 Oct 1990
• Country of Publication: United States
• Language: English

Related Subjects

70 PLASMA PHYSICS AND FUSION TECHNOLOGY
HYLIFE CONVERTER
WALL LOADING
ABLATION
DAMAGING NEUTRON FLUENCE
DESIGN
FIRST WALL
ICF DEVICES
IMPACT SHOCK
PRESSURE EFFECTS
SCALING LAWS
X RADIATION
ELECTROMAGNETIC RADIATION
IONIZING RADIATIONS
LASER FUSION REACTORS
NEUTRON FLUENCE
POWER DENSITY
RADIATIONS
THERMONUCLEAR DEVICES
THERMONUCLEAR REACTOR WALLS
THERMONUCLEAR REACTORS
700208* - Fusion Power Plant Technology- Inertial Confinement Technology