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T.A Fauzi Soelaiman
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Mechanical Engineering

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ANALISIS TERMOHIDROLIK ALIRAN AIR PENDINGIN PADA BERKAS EMPAT PIPA PEMANAS SUSUNAN SEBARIS MENGGUNAKAN PAKET PROGRAM FLUENT V4.25 Reinaldy Nazar; Aryadi Suwono; T.A Fauzi Soelaiman
Mesin Vol. 11 No. 3 (1996)
Publisher : Mesin

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Abstract

The FLUENT V4.25 program is the CFD (Computational Fluid Dynamics) simulation. It can be used for fluid flow and heat transfer analyses and others. Regarding the program, the test is needed to know the validity, to verify that the program will give good output. Based on the test using experimental data on four heated parallel rod bundles, the output FL UENT V4.25, it gave a good result, where the differences between calculation and experimental data are not significant. It is expected that the FLUENT V4. 25 program may achieve success in thermo-hydraulic analysis on other similar systems.
ANALISIS TERMOHIDROLIK ALIRAN AIR PENDINGIN PADA BERKAS EMPAT PIPA PEMANAS SUSUNAN SEBARIS MENGGUNAKAN PAKET PROGRAM FLUENT V4.25 Reinaldy Nazar; Aryadi Suwono; T.A Fauzi Soelaiman
Mesin Vol. 12 No. 2 (1997)
Publisher : Mesin

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Abstract

The FLUENT V4.25 program is the CFD (Computational Fluid Dynamics) simulation. It can be used for fluid flow and heat transfer analyses and others. Regarding the program, the test is needed to know the validity, to verify that the program will give good output. Based on the test using experimental data on four heated parallel rod bundles, the output FLUENT V4.25, it gave a good result, where the differences between calculation and experimental data are not significant. It is expected that the FLUENT V4.25 program may achieve success in thermohydraulic analysis on other similar systems.
KAJI TEORITIK ASPEK TERMOHIDROLIK REAKTOR RISET PADA DAYA 2 MW Reinaldy Nazar; Aryadi Suwono; T.A Fauzi Soelaiman
Mesin Vol. 13 No. 1 (1998)
Publisher : Mesin

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The thermohydraulic aspect utilization on a nuclear reactor is very dominant, because the system gives limitation on the reactor operation. Regarding the problem, theoretical analysis of thermohydraulic aspect is done for a research reactor of 2 MW with hexagonal configuration of fuel elements With an assumption that the power generation each fuel element is the same and the other facilities are neglected, the output of FLUENT V4.25 program gave information that theoretically this research reactor can be operated on thermal power of 2 MW.
Co-Authors Aryadi Suwono Reinaldy Nazar