Garuda - Garba Rujukan Digital

p-Index From 2021 - 2026

0.444

P-Index

This Author published in this journals

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

Published : 37 Documents Claim Missing Document

Claim Missing Document

Articles

1 2 3 4

Design Study of Thorium Cycle Based Long Life Modular Boiling Water Reactors Nuri Trianti; Zaki Su’ud; Eka Sapta Riyana
Indonesian Journal of Physics Vol 22 No 4 (2011): Vol. 22 No. 4, October 2011
Publisher : Institut Teknologi Bandung

Design study of long life (cycle) Boiling Water Reactor, which can be operated for 20-30 years of operation time without the necessity of refuelling during that period, has been performed. In shown in the previous study Th232-U233 cycle based fuel has potential for longer operation time in the thermal reactor domain. To increase reactor operation time and minimize excess-reactivity burnable poison may be used. Protactinium (Pa-231), Np-238, or gadolinium has good properties for such purpose. Here based on the previous study we select Protactinium and Gadolinium poisons to be used in the present study. 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 various moderation compositions can be achieved reactor core with longer operation time, 20 ~ 30 years operation without fuel shuffling or refuelling. Similarly Gadolinium has been successfully used to extend refuelling time and reduce excess reactivity during burnup period for both oxide fuel and nitride fuel.

Optimization of Small Pb-Bi Cooled Modified CANDLE Burnup based Long Life Fast Reactors Zaki Su'ud; Nur Asiah Aprianti; Rida Siti NM; Hiroshi Sekimoto
Indonesian Journal of Physics Vol 23 No 1 (2012): Vol. 23 No. 1, July 2012
Publisher : Institut Teknologi Bandung

In this study optimization of modified CANDLE burnup scheme based long life Pb-Bi Cooled Fast Reactors with natural Uranium as Fuel Cycle Input for small long life reactors has been performed. In this design the reactor cores are subdivided into several parts with the same volume in the axial directions. 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, i.e. shifted the core of I’th region into I+1 region after the end of 10 years burn-up cycle. In this paper we discuss the characteristics of several designs of small long life Pb-Bi cooled fast reactors with modified CANDLE burn-up scheme. Four power levels of 250MWt, 400MWt, 600MWt, and 800MWt were investigated. For 250MWt and 400MWt cores we employed 67.5% high fuel volume fraction nitride fuels with large pin diameter of 1.35 cm while for 600and 800MWt cores we employed 60% fuel volume fraction nitride fuel with 1.2 cm pin diameter. The results show that all cores show similar trend in k-eff pattern change, k-inf pattern change, conversion ratio pattern change, and U-238 and Pu-239 atomic density pattern changes. Maximum discharged burn-up is in the range of 26-33%HM, while peak power density is in the range of 340-410 W/cc.

Study Neutronic of Small Pb-Bi Cooled Non-Refuelling Nuclear Power Plant Reactor (SPINNOR) with Hexagonal Geometry Calculation Dwita Nur Krisna; Zaki Su'ud
Indonesian Journal of Physics Vol 23 No 1 (2012): Vol. 23 No. 1, July 2012
Publisher : Institut Teknologi Bandung

Nuclear reactor technology is growing rapidly, especially in developing Nuclear Power Plant (NPP). The utilization of nuclear energy in power generation systems has been progressing phase of the first generation to the fourth generation. This final project paper discusses the analysis neutronic one-cooled fast reactor type Pb-Bi is capable of operating up to 20 years without refueling. This reactor use Uranium Nitride Thorium as fuel and operating on power range 100– 500MWtNPPs. The method of calculation used a computer simulation program utilizing the SRAC. SPINNOR reactor design is designed with the geometry of hexagonal shaped terrace that radially divided into three regions, namely the outermost regions with highest percentage of fuel, the middle regions with medium percentage of fuel, and most in the area with the lowest percentage. SPINNOR fast reactor operated for 20 years with variations in the percentage of uranium-233 by 7%, 7.75% and 8.5%. Neutronik the calculation and analysis show that the design can be optimized in a fast reactor for thermal power output SPINNOR 300MWt with a fuel fraction 60% and variations of Uranium-233 enrichment of 7% - 8.5%

Skyrme-Extended-Thomas-Fermi Approach Method In Investigation of Nuclear Ground State Properties of 208Pb Yacobus Yulianto; Zaki Su'ud
Indonesian Journal of Physics Vol 27 No 1 (2016): Vol 27 No 1 (2016), July 2016
Publisher : Institut Teknologi Bandung

In this research, it is performed the nuclear ground state properties investigation of 208Pb by using the SETF method with SLy4 set parameters. The energy optimization calculation is performed using SETFA code. The SETFA results are in good agreement with the related experiment results, and also with the results of the HFBRAD and HFODD- HFBTHO codes. It is can be indicated that Skyrme-Extended-Thomas-Fermi method can be used to explain the nuclear ground state properties, especially even-stable nucleus.

The Study of Fluid on Rayleigh-Taylor Instability Phenomena using Finite Volume Particle (FVP) Method Nur Asiah Aprianti; Sparisoma Viridi; Zaki Su'ud; Koji Morata
Indonesian Journal of Physics Vol 26 No 2 (2015): Vol. 26 No. 2, December 2015
Publisher : Institut Teknologi Bandung

Rayleigh-Taylor instability phenomena were encountered in science world, both on a small scale and large scale (interstellar gas). Rayleigh-Taylor instability is the interpenetration of material that occurs when a fluid is above the other fluid with smaller mass density. The fluid which was originally located in the upper part will continuously broke down and the void is filled by a fluid which was originally located in lower part, so it looks like a bubble. In computational fluid dynamic field, this phenomenon is one of the benchmarks used to test the performance of buoyancy force on a numerical method. On the particle method, particularly, the Rayleigh-Taylor instability has been successfully simulated using Moving Particle Semi-implicit (MPS) method. Similar to the MPS, on this study, the Rayleigh-Taylor instability between the silicon oil and water which driven by buoyancy force was simulated using finite volume particle (FVP) method. From the simulation results it can be concluded that the shape of the bubble produced in the present calculation is similar to the results observed in the experiments and methods of MPS.

Startup Reaktor Cepat berpendingin Gas Berbahan Bakar UN-PuN dengan Daya 800 MWth Tri Siswandi Syahputra; Zaki Suud
POSITRON Vol 7, No 1 (2017)
Publisher : Fakultas Matematika dan Ilmu Pengetahuan Alam, Univetsitas Tanjungpura

Studi strategi startup reaktor cepat berpendingin helium dengan bahan bakar uranium alam dan campuran plutonium dari PWR telah dilakukan. Reaktor dengan keluaran daya menengah dioperasikan dengan pengisian ulang bahan bakar setiap 10 tahun selama 40 tahun beroperasi. Perhitungan dilakukan dengan menggunakan sistem pengkodean SRAC dan JENDL -33 library, dengan model teras cylindrical cell 2D R-Z. Reaktor didesain dengan strategi stratup pembakaran CANDLE (Constan Axial shape of Neutron flux, nuclide densities and power shape During Life of Energy producing reactor) yang dimodifikasi dalam keadaan non equilibrium state. Dalam skema ini, teras aktif dibagi menjadi region-1 sampai dengan region-10 arah aksial dengan volume yang sama dan 2 region arah radial dengan fuel fraction berbeda. Bahan bakar fresh Uranium alam awalnya dimasukkan ke dalam region- 1, sedangkan region lainnya diisi oleh campuran uranium alam dan spent fuel dari PWR. Setelah satu siklus operasi, dilakukan pergeseran region-1 ke region-2, region-2 ke region -3 dan seterusnya. Bahan bakar pada region -10 dibuang sedangkan region-1 akan diisi kembali oleh bahan bakar Uranium alam. Ukuran daya reaktor 800 MWth dengan variasi fraksi bahan bakar telah diselidiki. Perhitungan dilakukan terhadap desain teras reaktor yang menggunakan variasi fraksi bahan bakar di bagian dalam dan luar : 50%,55%; 55%,60%, dan 60%,65%. Reaktor dengan daya 800 MWth dengan fraksi bahan bakar 50,55% menunjukan desain yang optimal. Rasio antara puncak dengan daya rata-rata diperoleh nilai 1.57 arah radial dan 2.57 arah aksial.

The Modified Glas-Mosel Formula for Numerical Investigation of the Fusion Cross-Sections of (O-16)+(Ge-70,72,73,74,76) - A Preliminary Study Yacobus Yulianto; Zaki Su'ud
INDONESIAN JOURNAL OF APPLIED PHYSICS Vol 13, No 1 (2023): April
Publisher : Department of Physics, Sebelas Maret University

Show Abstract | Download Original | Original Source | Check in Google Scholar | DOI: 10.13057/ijap.v13i1.41577

Many intense experimental and theoretical studies have been performed to understand the behavior of fusion reactions, especially related to the barrier height of the interacting nuclei. This preliminary study would discuss a variation of the applicability of the Glas-Mosel formula with a little bit of modification applied to heavy systems. The modified Glas-Mosel formula has been utilized to calculate the fusion cross-sections of (O-16)+(Ge-70,72,73,74,76). To perform the differential and the optimization numerics, the Finite Difference and Nelder-Mead methods were applied to Fortran script-code respectively to assist the computational process. Referring to the obtained results, it can be indicated that the obtained results are in positive agreement with the experimental data. In addition, the modified Glas-Mosel formula proposed in this study has the capability to explain the experimental results or in predicting the fusion cross-section of nuclei. Further investigations are needed to get the crucial data to serve as a basic reference.

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

Title

Found 37 Documents
Search

Abstract

Abstract

Abstract

Abstract

Abstract

Abstract

Abstract

Title Search

Found 37 Documents Search

Abstract

Abstract

Abstract

Abstract

Abstract

Abstract

Abstract

Title

Found 37 Documents
Search