Thermal hydraulics analysis of LIBRA-SP target chamber

Journal Article · Tue Dec 31 00:00:00 EST 1996 · Fusion Technology

OSTI ID:447260

Mogahed, E A ^[1]

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1. Univ. of Wisconsin, Madison, WI (United States)

LIBRA-SP is a conceptual design study of an inertially confined 1000 MWe fusion power reactor utilizing self-pinched light ion beams. There are 24 ion beams which are arranged around the reactor cavity. The reaction chamber is an upright cylinder with an inverted conical roof resembling a mushroom, and a pool floor. The vertical sides of the cylinder are occupied by a blanket zone consisting of many perforated rigid HT-9 ferritic steel tubes called PERITs (PEr-forated RIgid Tube). The breeding/cooling material, liquid lead-lithium, flows through the PERITs, providing protection to the reflector/vacuum chamber so as to make it a lifetime component. The neutronics analysis and cavity hydrodynamics calculations are performed to account for the neutron heating and also to determine the effects of vaporization/condensation processes on the surface heat flux. The steady state nuclear heating distribution at the midplane is used for thermal hydraulics calculations. The maximum surface temperature of the HT-9 is chosen to not exceed 625{degree}C to avoid drastic deterioration of the metal`s mechanical properties. This choice restricts the thermal hydraulics performance of the reaction cavity. The inlet first surface coolant bulk temperature is 370{degree}C, and the heat exchanger inlet coolant bulk temperature is 502{degree}C. 4 refs., 6 figs., 2 tabs.

• OSTI ID: 447260
• Report Number(s): CONF-9606116-; ISSN 0748-1896; TRN: 97:005226
• Journal Information: Fusion Technology, Vol. 30, Issue 3; Conference: Annual meeting of the American Nuclear Society (ANS), Reno, NV (United States), 16-20 Jun 1996; Other Information: PBD: 1996
• Country of Publication: United States
• Language: English

Related Subjects

70 PLASMA PHYSICS AND FUSION
36 MATERIALS SCIENCE
ION BEAM FUSION REACTORS
DESIGN
ICF DEVICES
FEASIBILITY STUDIES
PLASMA CONFINEMENT
TARGETS
FERRITIC STEELS
LIGHT IONS
LITHIUM
LEAD
LIQUID METALS
HEAT EXCHANGERS
REACTOR COOLING SYSTEMS
TUBES
HYDRAULICS
THERMAL ANALYSIS
SURFACE PROPERTIES
NUMERICAL DATA