Articles
<![CDATA[Pengembangan Kode Komputer untuk Homogenisasi Sel Bahan Bakar Nuklir yang Diperkaya untuk Reaktor Termal ]]>
<![CDATA[Novitrian Novitrian]]>;
<![CDATA[Zaki Su’ud]]>;
<![CDATA[Sutrisno Sutrisno]]>
<![CDATA[ Indonesian Journal of Physics Vol 13 No 1 (2002): Vol. 13 No.1, Januari 2002 ]]>
Publisher : <![CDATA[Institut Teknologi Bandung ]]>
Show Abstract
|
Download Original
|
Original Source
|
Check in Google Scholar
|
Full PDF (146.643 KB)
<![CDATA[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.]]>
<![CDATA[Design Study of Modular Lead-Bismuth Cooled Fast Reactors with Nitride Fuel ]]>
<![CDATA[Abu Khalid Rivai]]>;
<![CDATA[Zaki Su’ud]]>;
<![CDATA[Ferhat Aziz]]>
<![CDATA[ Indonesian Journal of Physics Vol 14 No 4 (2003): IJP Vol. 14 No. 4, October 2003 ]]>
Publisher : <![CDATA[Institut Teknologi Bandung ]]>
Show Abstract
|
Download Original
|
Original Source
|
Check in Google Scholar
|
Full PDF (144.03 KB)
<![CDATA[This paper discusses designs of modular lead-bismuth cooled fast reactors fueled with uranium nitride. The power range of the reactors under study was between 75 MWt and 700MWt. The reactors were designed by optimizing the use of natural uranium blanket and nitride fuel to prolong the fuel cycle. The fuels were enriched uranium nitride which can be used without refueling for 10 years. This study was done on pancake, balance and tall cylindrical types of cores. The results of calculation showed that the maximum excess reactivity in all core designs under study was 0.36 dollar. As for the burnup at EOC, the highest was in the 700 MWt balance core type with 11.95%, and the lowest was at 75MWt pancake core with 2.4% burnups. Capability of burnup in general was quite high. The maximum peak power density obtained was 324 W/cc, i.e. in 700 MWt tall type of core. The peak power densities of these reactores were well below those of the average fast reactors, which were indicative of good safety and controllability of operation.]]>
<![CDATA[Proyeksi Kernel GCM pada Sembarang Fungsi ]]>
<![CDATA[Rizal Kurniadi]]>;
<![CDATA[Marsongkohadi Marsongkohadi]]>;
<![CDATA[Zaki Su’ud]]>;
<![CDATA[Triyanta Triyanta]]>
<![CDATA[ Indonesian Journal of Physics Vol 14 No 4 (2003): IJP Vol. 14 No. 4, October 2003 ]]>
Publisher : <![CDATA[Institut Teknologi Bandung ]]>
Show Abstract
|
Download Original
|
Original Source
|
Check in Google Scholar
|
Full PDF (70.713 KB)
<![CDATA[The GCM kernel projection on arbitrary function is a technique to solve Schredinger integro-differential equation. The Basic idea is making eigen value equation from Schroedinger equation by projecting the GCM kernel into no orthonormal functions. In this paper the technique is presented to calculate ground state energy of deuteron.]]>
<![CDATA[Development of Single-Board Computer Based Web Server for Physics Related Instrumentation and Its More General Usage ]]>
<![CDATA[Endarko Endarko]]>;
<![CDATA[Zaki Su’ud]]>
<![CDATA[ Indonesian Journal of Physics Vol 14 No 3 (2003): Vol. 14 No.2, Juli 2003 ]]>
Publisher : <![CDATA[Institut Teknologi Bandung ]]>
Show Abstract
|
Download Original
|
Original Source
|
Check in Google Scholar
|
Full PDF (209.443 KB)
<![CDATA[The web server single-board provides web access to some digital I/O and serial I/O signals without the need for assistance from external PCs or UNIX computers. It’s stand-alone device with real-time networking kernel, a TCP/IP stack, and HTTP web server. This project started partly as an excuse to use a new microprocessor and partly to settle a long-standing argument about the possibility of delivering web pages with a commercial microcontroller. The Atmel AT90S8515 microprocessor looked exciting with it’s low power RISC processor, 8 KB flash program memory, 512 bytes of EEPROM, 512 bytes of RAM, 32 I/O lines, and a built-in UART. The proposed device is designed application for physics related instrumentation and its more general usage.]]>
<![CDATA[Optimization of small and very small long life Pb-Bi Cooled Fast reactors ]]>
<![CDATA[Zaki Su’ud]]>
<![CDATA[ Indonesian Journal of Physics Vol 15 No 2 (2004): Vol. 15 No.2, April 2004 ]]>
Publisher : <![CDATA[Institut Teknologi Bandung ]]>
Show Abstract
|
Download Original
|
Original Source
|
Check in Google Scholar
|
Full PDF (93.698 KB)
<![CDATA[In this paper optimization of small and very small nuclear power plant is discussed. The reactor is subjected to fulfill fourth generation nuclear power plant criteria. For very small nuclear power reactor, constraining the reactivity swing to be smaller than one dollar during operation usually result in small power density, relatively large core and low burnup level. One key concept in the present discussion is by the use of tight lattice and large fuel diameter so that the fuel volume fraction becomes large and pressure drop is still reasonable. The central part of the core is filled by fertile material for minimization of excess reactivity during reactor operation. By using this concept small but effective nucclear power plant can be designed. The core can achieve burnup of about 13 % heavy metal and the height and diameter of the active core is much smaller than 1 meter.]]>
<![CDATA[Design Study on Ship Based Small Nuclear Power Reactors ]]>
<![CDATA[Zaki Su'ud]]>;
<![CDATA[Dian Fitriyani]]>
<![CDATA[ Indonesian Journal of Physics Vol 15 No 3 (2004): Vol. 15 No. 3, July 2004 ]]>
Publisher : <![CDATA[Institut Teknologi Bandung ]]>
Show Abstract
|
Download Original
|
Original Source
|
Check in Google Scholar
|
Full PDF (62.369 KB)
<![CDATA[The results of conceptual design study on ship based small nuclear power reactors are presented. The reactors are basically lead-bismuth cooled fast power reactors with long refueling interval and low reactivity swing. Here we optimized the designs to achieve the feasibility to be operated under sea wave movement. The system use loop type with relatively large coolant pipe above reactor core. The reactors do not use IHX, so that the heat from primary coolant system directly transferred to water-steam loop through steam generator. The reactors are capable to be operated in difference power level during night and noon. This feature is necessary because in some rural area the main use of the reactors is just to support home electricity. The reactors however can also be used totally or partially to produce clean water through desalination of seawater. Due to the influence of sea wave movement the analysis have to be performed in three dimensional analysis. We found that the effect of the seawater movement is significant in changing flow pattern distribution and outlet temperature distribution.]]>
<![CDATA[Alpha-cluster Model for 6Li, 8Be and 12C Nuclei within the Framework of the Generator Coordinate Approach ]]>
<![CDATA[Rizal Kurniadi]]>;
<![CDATA[Marsongkohadi Marsongkohadi]]>;
<![CDATA[Zaki Su’ud]]>;
<![CDATA[Triyanta Triyanta]]>
<![CDATA[ Indonesian Journal of Physics Vol 16 No 3 (2005): Vol. 16 No. 3, July 2005 ]]>
Publisher : <![CDATA[Institut Teknologi Bandung ]]>
Show Abstract
|
Download Original
|
Original Source
|
Check in Google Scholar
|
Full PDF (142.001 KB)
<![CDATA[The ground and excited states of 6Li, 8Be and 12C nuclei are investigated using the generator- coordinate method (GCM) involving (αd), (αα) and (3α) – clusters structures, respectively. It is assumed that the α and d particles are not structureless point particles, rather are represented by a certain four-nucleon and two-nucleon wave functions, respectively, so that the generating function depends on the possible nucleon configurations. The nucleonic wave functions are defined through the harmonic oscillator shell model (HOSM), whereas the nucleon-nucleon interaction is represented by a Gaussian-shape potential. The GCM kernels are projected out on nonorthonormal functions, instead of performing the standard Gram-Schmidt orthonormalization procedure. The total wave function is expanded in terms of these functions to obtain standard eigenvalue equation in nonorthonormal basis. Calculated spectroscopic properties are presented to be in excellent agreement with the experimental values and better than other calculation methods, such as the variational Monte Carlo (VMC), and the Green’s function Monte Carlo (GFMC).]]>
<![CDATA[Design Study of Ship Based Nuclear Power Reactor (Core Geometry Optimization) ]]>
<![CDATA[Dian Fitriyani Fitriyani]]>;
<![CDATA[Zaki Su'ud]]>
<![CDATA[ Indonesian Journal of Physics Vol 16 No 4 (2005): Vol. 16 No. 4, October 2005 ]]>
Publisher : <![CDATA[Institut Teknologi Bandung ]]>
Show Abstract
|
Download Original
|
Original Source
|
Check in Google Scholar
|
Full PDF (102.495 KB)
<![CDATA[Preliminary design study of ship based nuclear power reactor has been performed. The results of thermo hydraulics analysis is presented and the core geometry optimization is reported. The reactors are basically lead-bistmuth cooled fast reactor using nitride fuels to enhance neutronics and safety performance. Some design modification are performed for feasibility of operation under ship dynamics caused by external forces from the marine environment such as wind, waves and tidal current that impressing reactor core performance. The basic reactor characteristics is that the power level is 100-200 MWth and excess reactivity is about 1$. In this study, the steady state thermo hydraulic calculation was further performed to investigate the effect of core geometry on the design performance of the proposed ship based reactors under variation of ship oscillation about 0o– 40o. The calculation result show that balance (square) core is the convenient core geometry for the best thermo hydraulic performance optimization of design. The ship oscillations influence to balance core temperature distribution is small enough compared to low core, while pressure drop even also not as high as at tall core. The variations of total coolant flow-rate across the core are also estimated to investigate the natural circulation level and necessary pumping power for the proposed design.]]>
<![CDATA[Preliminary Design Study of Thorium(Th) and Protactinium ( 231 Pa) Based Fuel for Tight Lattice Long Life BWR ]]>
<![CDATA[Eka Sapta Riyana]]>;
<![CDATA[Zaki Su’ud]]>
<![CDATA[ Indonesian Journal of Physics Vol 16 No 4 (2005): Vol. 16 No. 4, October 2005 ]]>
Publisher : <![CDATA[Institut Teknologi Bandung ]]>
Show Abstract
|
Download Original
|
Original Source
|
Check in Google Scholar
|
Full PDF (146.791 KB)
<![CDATA[A preliminary design study for the utilization of thorium based fuel loaded with 231Pa on tight lattice BWR type reactor has been performed. Protactinium-231 has very interesting neutronic properties, which enable the core to reduce initial excess-reactivity and simultaneously increase production of 233U to 231Pa in burn-up process. Optimizations the content of 231Pa in the core enables the BWR core to sustain enough reactivity for long period of time with reasonable burn-up reactivity swing. Based on the optimization of fuel element composition (Th and Pa) in low moderation environment (tight lattice core) can be achieved reactor core with longer operation time, 20 ~ 30 years operation without fuel shuffling or refueling, with average power densities of about 35 watt/cc.]]>
<![CDATA[Design of The 200 MW(t) Pb-Bi Cooled Nuclear Fast Reactor For Steam Membrane Reforming Hydrogen Production ]]>
<![CDATA[Epung Saepul Bahrum]]>;
<![CDATA[Zaki Su’ud]]>;
<![CDATA[Abdul Waris]]>;
<![CDATA[Bambang Ari Wahjoedi]]>
<![CDATA[ Indonesian Journal of Physics Vol 17 No 4 (2006): Vol. 17 No. 4, October 2006 ]]>
Publisher : <![CDATA[Institut Teknologi Bandung ]]>
Show Abstract
|
Download Original
|
Original Source
|
Check in Google Scholar
|
Full PDF (307.98 KB)
<![CDATA[Design study of the 200 MW(t) Pb-Bi cooled nuclear fast reactor for steam membrane reforming hydrogen production has been proposed. The design base on neutronic, steady state thermalhydraulic and safety examination of the 200 MWt Pb-Bi cooled fast nuclear reactor. For balance cylindrical core demonstrated that at flowrate 7000 kg s-1 and inlet coolant temperature of 350 0C yield average and maximum coolant outlet temperature of 552 and 621 0C. The safety analysis confirm at that situation the coolant and fuel cladding maximum temperature lower than coolant boiling and cladding melting temperature. The 552 0C average coolant outlet temperature corresponds to maximum reaction temperature of the steam membrane reforming which is close to 550 0C. We proposed design of the 200 MW(t) Pb-Bi cooled balance cylindrical core nuclear fast reactor for steam membrane reforming hydrogen production. The configuration of the design is Pb-Bi cooled nuclear fast reactor and steam membrane hydrogen production unit coupled with intermediate heat exchanger. One of the intermediate heat exchanger functions is to protect nuclear reactor when an explosion accident occur in the hydrogen production unit.]]>
