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All Journal POSITRON Jurnal Sains dan Pendidikan Fisika Jurnal Forum Nuklir Jurnal Pengembangan Energi Nuklir JURNAL FISIKA Jurnal Fisika Unand JURNAL ISTEK Jurnal Penelitian Sains INDONESIAN JOURNAL OF APPLIED PHYSICS Saintifik : Jurnal Matematika, Sains, dan Pembelajarannya Indonesian Journal of Physics (IJP)

Zaki Suud

Institut Teknologi Bandung, Jalan Terusan Ryacudu, Way Hui, Lampung Selatan, Indonesia

Author-ID : 5770108

Astronomy Chemistry Computer Science & IT Decision Sciences, Operations Research & Management Earth & Planetary Sciences Education Electrical & Electronics Engineering Energy Engineering Environmental Science Industrial & Manufacturing Engineering Materials Science & Nanotechnology Mathematics Physics Social Sciences Other

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Preliminary Study of Steels Corrosion Phenomena in Liquid Lead-Bismuth using Molecular Dynamics Methods Alan Maulana; Zaki Su'ud; Hermawan K. Dipojono; Khairurrijal Khairurrijal
Indonesian Journal of Physics Vol 18 No 1 (2007): Vol. 18 No. 1, January 2007
Publisher : Institut Teknologi Bandung

Show Abstract | Download Original | Original Source | Check in Google Scholar | Full PDF (110.045 KB)

One of the prospective coolant material which can be used in the forth generation nuclear reactor is a liquid lead-bismuth. This coolant has inherent safety capability, economical, and able to burn their own nuclear waste. The problem of using this coolant is corrosion phenomena of steel occurred in the interaction with liquid lead-bismuth especially at high temperatures. Corrosion in this study is assumed as diffusion phenomena of leads or bismuths into the surface of steel. This phenomenon have been studied by molecular dynamic methods. As the first step to this investigation, the molecular dynamic program called Moldy has been used to simulate pure iron and lead system. The molecular dynamic simulation result of pure Fe system at 0 K showed that the peaks positions of radial distribution function is in a good agreement with the result from experiment. The deviation of the peaks position resulted from simulation and experiment is about 0.5%. The simulation result of Pb system showed no significant different with the result from experiment. The simulation also shows the broadening of the curves of radial distribution function and lowering the intensity at high temperature. These results indicate that the atomic positions of the system are distributed randomly.

Design Study of Long Life Pb-Bi Cooled Reactors With Natural Uranium as Fuel Cycle Input Using Radial Fuel Shuffling Strategy Rida Siti NM; Zaki Su'ud
Indonesian Journal of Physics Vol 18 No 1 (2007): Vol. 18 No. 1, January 2007
Publisher : Institut Teknologi Bandung

Show Abstract | Download Original | Original Source | Check in Google Scholar | Full PDF (75.404 KB)

Conceptual design study of Pb-Bi cooled fast reactors which fuel cycle need only natural uranium input has been performed. In this design the reactor cores are subdivided into several parts with the same volume. The region with natural uranium is put in the central core while the outer region is arranged with increasing plutonium content. However, in some cases the region with natural uranium content can be put in the most outer part of the core. The arrangement of the plutonium content considers the criteria that the fuel in the certain part must be fit for fresh fuel in the next higher enrichment region. Therefore at the end of a long life operation we just need to supply natural uranium fuel to the blanket region and move other regions properly to the next regions. As an example, using SRAC and FI-ITB CHI code system we obtained a core with 15-20 years life time per sub cycle.

Corrosion Study of Steels In Liquid Lead-Bismuth Cooled Nuclear Reactors by Computer Simulation using Moldy Code Alan Maulana; Zaki Su'ud; Hermawan K. Dipojono; Khairurrijal Khairurrijal
Indonesian Journal of Physics Vol 18 No 2 (2007): Vol. 18 No. 2 April 2007
Publisher : Institut Teknologi Bandung

The corrosion of steel in liquid lead-bismuth has been studied by computer simulation using MOLDY code. The diffusion processes among atoms are assumed to be the key issues to understand the corrosion mechanism microscopically. In order to simulate these diffusion processes, the inter-atomic potential between Fe-Fe, Pb-Pb, Bi-Bi, Cr-Cr and Ni-Ni are assumed to obey the Lennard-Jones potential. The Lennard-Jones potential parameters of above pairs of atom have been derived by fitting the data available in the literature with the Lennard-Jones equation. The initial positions of the system are taken from the crystal structures data including the cell parameters. The simulation cell was a box with the volume 60x30x30 Å3 that were filled by 2864 atoms. Nickel and chromium atoms were substituted into Fe crystal with the percentage 10% and 16 % respectively to construct the systems of SS-316 which contacted by 50%Pb-50%Bi. The molecular dynamic simulations have been carried out for surface interaction between steel crystal with liquid lead-bismuth for several temperatures. After done the above simulation, the simulation is then tried by using 45%Pb-55%Bi (Pb-Bi Eutectic). The results of molecular dynamic simulations for several temperatures and the effect of variation of Pb and Bi above will be presented in this paper.

Feasibility Design Study of Long Life BWR with Natural Uranium/Thorium as Fuel Cycle Input Zaki Su'ud; Rijal Kurniadi; Rida SNM; Zuhair Zuhair
Indonesian Journal of Physics Vol 20 No 1 (2009): Vol. 20 No. 1, January 2009
Publisher : Institut Teknologi Bandung

Feasibility design study of Long Life BWR with natural uranium/thorium as fuel cycle input has been performed. The reactor core is divided into 6 equal regions in radial direction. The fresh fuel is first loaded into the most outer region then shifted to the center of the core, and from there shifted to the nearby region in the outward direction. Nitride fuel is employed in the core to get better criticality and conversion/breeding ratio. The results show that uranium fuel combined with low moderating ratio environment is superior to make the system critical.

Fission Yield Calculation Method and its Effect in Nuclear Fuel Cell Homogenization Calculation Zaki Su’ud; M. Ali Shafii; Rida SNM
Indonesian Journal of Physics Vol 20 No 2 (2009): Vol. 20 No. 2, April 2009
Publisher : Institut Teknologi Bandung

Zero burn-up core capability can eliminate possible super prompt critical accident and make possible of inherent safety feature based on reactivity feedback mechanism. In this concept the maximum excess reactivity is limited below 1 $ of reactivity so that possibility of super prompt accident such as in Chernobyl accident case can be eleminated. This is however need high quality of system analysis, and in this study the effect of fission yield calculation method on the nuclear fuel cell homogenization process is investigated and discussed. This study use SRAC code system to investigate the efect of reactor dependent fission yield distribution calculation. Calculation restults show that this process will has important improvement effect for long life high burnup core.

Preliminary design study of Long-life Gas Cooled Fast Reactor With Modified CANDLE Burnup Scheme Nur Asiah A; Merry Yanti; Zaki Su’ud; Menik A.; H. Sekimoto
Indonesian Journal of Physics Vol 20 No 4 (2009): Vol. 20 No. 4, October 2009
Publisher : Institut Teknologi Bandung

In this paper, preliminary design study of Gas Cooled Fas Reactors with Natural Uranium as Fuel Cycle Input has been performed. Gas Cooled Fast Reactor is slightly modified by employing modified CANDLE burnup scheme so that it can use Natural Uranium as fuel cycle input. The natural uranium is initially put in region 1, after one cycle of 10 years of burn-up it is shifted to region 2 and the region 1 is filled by fresh natural uranium fuel. This concept is basically applied to all regions. In this case the system has been applied to many power level which results relatively flexible discharge burn-up level up from about 20%HM to 30 %HM.

Study of Transuranium Recycling in PWR with 3-D Burnup Analysis using SRAC-COREBN Code Abdul Waris; T. Rahmanto; Imam Taufiq; Rizal Kurniadi; Zaki Su’ud
Indonesian Journal of Physics Vol 20 No 4 (2009): Vol. 20 No. 4, October 2009
Publisher : Institut Teknologi Bandung

In the light of proliferation resistance and terrorism issues several nuclear energy authorities and experts have suggested not to separate plutonium and minor actinides during the nuclear spent fuel reprocessing. Along the lines of this recommendation, a study of transuranium recycling in pressurized water reactor (PWR) with 3 dimensional burnup analysis by using SRAC-COREBN code has been carried out. The results show that by recycling of 8%, 10%, and 12 % of plutonium and minor actinides in PWR, the necessary uranium enrichment in loaded enriched uranium fuel of each scenario can be reduced to 2.7%, 1.52%, and 1.32%, correspondingly. In addition to this, the amount of loaded uranium fuel diminishes considerably with the increasing of the amount of recycled of plutonium and minor actinides.

Parallel Burnup Analysis of Long-life Fast Reactors Using Multi-core Programming Imam Taufiq; Zaki Su'ud; Abdul Waris; Mitra Djamal
Indonesian Journal of Physics Vol 21 No 1 (2010): Vol. 21 No. 1, January 2010
Publisher : Institut Teknologi Bandung

A scalable parallel program for burnup analysis of long-life fast reactor has been succesfully built. The scalability test was conducted by comparing the program performance on dual-core and quad-core platforms. The best speedup gain were 1.72 on dual core 2.0 GHz, 3.58 on quad-core 2.4 GHz and 3.05 on quad-core 3.2 GHz. The slight drop of the speedup on quad-core 3.2 GHz could be well explained in connection with communication-time needed in running parallel version of the program.

Source Term Calculation of Small Pb-Bi Cooled Non-Refueling Nuclear Power Reactor 20 MWe (SPINNOR 20MWe) Imron Imron; Zaki Su’ud; Ari Darmawan Pasek
Indonesian Journal of Physics Vol 21 No 2 (2010): Vol. 21 No. 2, April 2010
Publisher : Institut Teknologi Bandung

Source term calculation of small Pb-Bi cooled, 15 years non-refueling nuclear reactor 20 MWe (SPINNOR 20MWe) has been performed. The study is limited on activity, toxicity, thyroid and whole body dose. The reactor has an average power density of 187 watt/cm3 with near zero postulated accident propability. The LOCA probability less than that of PWR type because of low pressure condition in the Reactor vessel. The coolant freezing in room temperature can protect nuclide from escaping. Antisipated accident by design capable to protect reactor from unprotected transient over power and unprotected loss of flow accident without scram. In hipotetik scenario accident, there is a sabotage in vessel and core melt when cooling system is lost. Core inventory factor on final cycle is 3,69E+9 Ci/MWth. Except elemental iodine and noble gas, all radionuclides were traped in containment. The source term in containmen 1,8 h after accident for Noble Gas group is 2,38E+09 Ci, Halogen group is 5,12E+08 Ci, Alkali metal group is 3,04E+08 Ci, Tellerium group is 3,99E+07 Ci, BaSr group is 6,80E+07 Ci, Noble Metal group is 2,91E+06 Ci, Lanthanide group is 1,72E+06 Ci, Cerium group is 8,12E+07 Ci. Np-237 is the longest for clearance time about 16.500 years, the most toxic is Xe-138 with α/D reach 7,38E+19. The Source term is used for estimate thyroid dose, in EPZ is 0.89 rem and in LPZ is 0.055 rem below limit constrain PWR 180 rem and 130 rem. The whole body dose in EPZ and LPZ is 0,00132 rem dan 0.000269 rem with PWR Standard 9,74 rem dan 8,54 rem. Based on acceptece criteria of PWR type, the safety requirement of SPINNOR 20MWe is achieved.

Comparative Study on 233U and Plutonium Utilization in Molten Salt Reactor Abdul Waris; Indarta Kuncoro Aji; Yanti Yulianti; Muhamad Ali Shafii; Imam Taufiq; Zaki Su'ud
Indonesian Journal of Physics Vol 21 No 3 (2010): Vol. 21 No. 3, July 2010
Publisher : Institut Teknologi Bandung

A comparative study on 233U and Pu utilization in a molten salt reactor (MSR) FUJI-12 has been conducted. Originally, FUJI-12 uses LiF , BeF2 , ThF4 and 233UF4 as fuel. In this study, we have evaluated the use of reactor grade plutonium and weapon grade plutonium beside 233U as the fuel of reactor. The need of 233U concentration for criticality is about 0.34%. In contrast, the demand of the reactor grade plutonium and the weapon grade plutonium fractions for criticality is around 3.0% and 0.96%, correspondingly. The neutron flux in the thermal energy region for 233U fuel case is higher than in Pu fuel cases due to larger value of the average number of neutrons produced per neutron absorbed in 233U fuel than that of 239Pu fuel, and may also because of the hardening of the neutron spectrum owing to plutonium utilization in thermal reactor.

Co-Authors Abdul Waris Abu Khalid Rivai Alan Maulana Alan Maulana Ari Darmawan Pasek Bambang Ari Wahjoedi Dian Fitriyani Dian Fitriyani Dwita Nur Krisna Eka Sapta Riyana Eka Sapta Riyana Elsa Yolanda Putri Endarko Endarko Epung Saepul Bahrum Ferhat Aziz Feriska Handayani Irka, Feriska Handayani Fitriah Bidalo H. Sekimoto Hermawan K. Dipojono Hiroshi Sekimoto Imam Taufiq Imam Taufiq Imam Taufiq Imron Imron Indarta Kuncoro Aji Josua Timotius Manik Khairurrijal Khairurrijal Koji Morata M. Ali Shafii M. I. A. Abidin Marsongkohadi Marsongkohadi Marsongkohadi Marsongkohadi Menik A. Merry Yanti Mitra Djamal Moh Nurul Subkhi Mohammad Ali Shafii Muhamad Ali Shafii Novitrian Novitrian Nur Asiah A Nur Asiah Aprianti Nur Asiah Aprianti Nuri Trianti Nurlina Nurlina Ramadhan, Andri Rida Siti NM Rida Siti NM Rida SNM Rijal Kurniadi Rizal Kurniadi Rizal Kurniadi Rizal Kurniadi Sari Novalianda Sidik Permana Sparisoma Viridi Sunarko Sunarko Sutrisno Sutrisno T. Rahmanto Tri Siswandi Syahputra Triyanta Triyanta Triyanta Triyanta Victor Reynaldi Yacobus Yulianto Yacobus Yulianto Yacobus Yulianto Yanti Yulianti Zuhair Zuhair

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