Heat Transfer Through Two Phase Flow On The Porous Material

HEAT TRANSFER THROUGH TWO PHASE FLOW ON THE POROUS MATERIAL

Ign. Djoko Irianto
Center for Nuclear Technology Assessment - BATAN
Email: igndjoko@batan.go.id
ABSTRACT
The experiment using porous heat pipe model with internal heat generation has been done to study the heat transfer characteristic on the porous material. Heat pipe model comprises a quartz tube with 300 mm length, 20 mm inner diameter and 3.5 mm thickness. Porous media were simulated using small steel balls. Working fluid which is used are water, propanol, and octane. Internal heat generation was simulated using high frequency induction. The experiment results showed that if boils have not occurred, heat transfer occurred by conduction process. Using the higher power, two phase flows will occur so that the heat transfer coefficient will increase.

Keywords : heat pipe, porous material, heat transfer, two phase flow
Published : Proceedings "XVI^th National Symposium On Physics And ASEANIP Regional Seminar On The Physics Of Metals and Alloys", Bandung, December 12-14, 1996, ISBN 979-8580-14-1

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THERMAL-HYDRAULIC ANALYSIS OF THE NUCLEAR BATTERY COOLANT SYSTEM

THERMAL-HYDRAULIC ANALYSIS OF THE NUCLEAR BATTERY COOLANT SYSTEM
Ign. Djoko Irianto, Budi S., Sarwo D.Danupoyo, Ahmad Syaukat, Budi Santoso
Center for Nuclear Technology Assessment - BATAN
Email: igndjoko@batan.go.id
ABSTRACT
THERMAL-HYDRAULIC ANALYSIS OF THE NUCLEAR BATTERY COOLANT SYSTEM. Thermal-hydraulic analysis has been done for the coolant system of the nuclear battery, which utilizes heat pipes as the primary coolant system for heat removal from the reactor core to the secondary coolant system. This paper analysis the thermal hydraulic aspect of the nuclear battery coolant system by constructing the design model for heat pipe, as the primary coolant system, and analyzing the energy balance on the secondary coolant system. The model refers to the nuclear battery operated at a power of 2400 kW(t) and nominal core graphite temperature of 550 oC. The wrapped screen wick type heat pipe 3 m length and 5 cm diameter with potassium as working fluid has a maximum axial heat flow of 102957 W at operating temperature 482 oC. Using toluene as working fluid at maximum temperature of 370 oC the secondary coolant system equipped with a regenerator has a thermal efficiency of 26 %. The nuclear battery with capacity of 2400 kW(t) requires 24 heat pipes.

Keywords : Thermal-Hydraulic Analysis, Nuclear Battery, Primary coolant System, Heat Pipe, Thermal Efficiency
Published : Proceeding "Seminar Seperempat Abad Reaktor Nuklir Mengabdi Ilmu Pengetahuan dan Teknologi", Bandung, 16-17 Oktober 1989, ISSN No. : 1410-1769

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