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Novitrian Novitrian
Departemen Fisika FMIPA, Institut Teknologi Bandung Jl. Ganesa 10 Bandung 40132
Astronomy Computer Science & IT Earth & Planetary Sciences Electrical & Electronics Engineering Energy Engineering

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Pengembangan Kode Komputer untuk Homogenisasi Sel Bahan Bakar Nuklir yang Diperkaya untuk Reaktor Termal Novitrian Novitrian; Zaki Su’ud; Sutrisno Sutrisno
Indonesian Journal of Physics Vol 13 No 1 (2002): Vol. 13 No.1, Januari 2002
Publisher : Institut Teknologi Bandung

Show Abstract | Download Original | Original Source | Check in Google Scholar | Full PDF (146.643 KB)

Abstract

Like in the most nuclear cell homogenization, integral transport equation is also used to solve the neutron transport problem, especially by using collision probability method. This method has the advantage that for relatively simple geometry the angular integration may be carried out analytically. Neutron transport equation was solved in accordance with the physical neutron characteristic in its energy range. The neutron spectrum calculation used 70 energy group and for thermal energy range the energy was divided into 48 energy groups.For calculation in the fast energy range we used microscopic cross section data from SLAROM library, while for thermal energy range we used experiment data from ENDF/B VI and then we interpreted it with the used of Code System NJOY97.0. As an example calculation we considered one-dimensional cylindrical cell which was divided into 3 regions i.e, for fuel, cladding, and coolant. The nuclear cell homogenization calculation was treated by the use of linear equation.
Evaluation of Pb-Bi-Water Direct Contact Boiling Flow in a Vertical Circular Channel using Drift-Flux Model Novitrian Novitrian; Minoru Takahashi
Indonesian Journal of Physics Vol 19 No 4 (2008): Vol. 19 No. 4, October 2008
Publisher : Institut Teknologi Bandung

Show Abstract | Download Original | Original Source | Check in Google Scholar | Full PDF (187.308 KB) | DOI: 10.5614/itb.ijp.2008.19.4.1

Abstract

The characteristics of Pb-Bi-water boiling two-phase flow were investigated in a vertical circular channel. Water was injected into Pb-Bi to circulate Pb-Bi in a loop with an effect of steam lift pump. Pb-Bi flow rates were measured and analytically estimated using balance condition between buoyancy force and pressure losses. The drift-flux model was used to determine void fraction with assumption that bubble sizes were dependent on the fluid surface tension and density ratio of Pb-Bi to steam and water mixture. The result of analysis shows that the deviation from the experimental data was less than 20%.
Co-Authors Minoru Takahashi Sutrisno Sutrisno Zaki Suud