Ikuti
Mohammad Ali Shafii
Mohammad Ali Shafii
Department of Physics, Andalas University
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Judul
Dikutip oleh
Dikutip oleh
Tahun
Multi-criteria decision making for nuclear power plant selection using fuzzy AHP: Evidence from Indonesia
AG Abdullah, MA Shafii, S Pramuditya, T Setiadipura, K Anzhar
Energy and AI 14, 100263, 2023
162023
Nuclear fuel cell calculation using collision probability method with linear non flat flux approach
MA Shafii, Z Su’ud, A Waris, N Kurniasih
Scientific Research Publishing, 2012
122012
Studi Awal Desain Reaktor Cepat Berpendingin Gas Berbasis Bahan Bakar Uranium Alam
M Ariani, MA Shafii, AG Abdullah, Z Su’ud
Proceeding Seminar dan Workshop Nasional Pendidikan Teknik Elektro (SWNE), 93-98, 2010
82010
Effect of Fuel Fraction on Small Modified CANDLE Burn‐up Based Gas Cooled Fast Reactors
M Ariani, Z Su’ud, A Waris, Khairurrijal, N Asiah, MA Shafii
AIP Conference Proceedings 1325 (1), 249-252, 2010
72010
Comparative study on 233U and plutonium utilization in molten salt reactor
A Waris, IK Aji, Y Yulianti, MA Shafii, I Taufiq, Z Suud
Indonesian Journal of Physics 21 (3), 77-81, 2010
72010
Effects of land cover change and deforestation on rainfall and surface temperature in new capital city of Indonesia
R Safitri, M Marzuki, MA Shafii, H Yusnaini, R Ramadhan
Jurnal Penelitian Pendidikan IPA 8 (6), 2849-2858, 2022
62022
Characteristics of rain attenuation for microwave-to-terahertz waveband from raindrop size distribution observation in Indonesia
M Yoseva, H Hashiguchi, M Vonnisa, L Luini, S Nugroho, MA Shafii
2019 PhotonIcs & Electromagnetics Research Symposium-Spring (PIERS-Spring …, 2019
62019
Neutron flux distribution calculation for various spatial mesh of finite slab geometry using one-dimensional diffusion equation
MA Shafii, WW Yunanda, D Fitriyani, S Pramuditya
AIP Conference Proceedings 2180 (1), 2019
52019
The Pij matrix and flux calculation of one-dimensional neutron transport in the slab geometry of nuclear fuel cell using collision probability method
MA Shafii, J Usman, SHJ Tongkukut, AG Abdullah
MATEC Web of Conferences 197, 02006, 2018
52018
Analysis of neutron fission reaction rate in the nuclear fuel cell using collision probability method with non flat flux approach
MA Shafii
Journal of Physics: Conference Series 877 (1), 012013, 2017
52017
Perhitungan Penampang Lintang Mikroskopik dalam Sel Bahan Bakar Nuklir
MA Shafii
Spektra: Jurnal Fisika dan Aplikasinya 16 (1), 23-27, 2015
52015
Characteristics of neutron diffusion coefficient as a function of energy group in the one-dimensional multi-group diffusion equation of finite slab reactor core
MA Shafii, I Zakiya, D Fitriyani, SHJ Tongkukut, AG Abdullah
Journal of Physics: Conference Series 1869 (1), 012202, 2021
42021
Loss of load probability calculation for west java power system with nuclear power plant scenario
ID Azizah, AG Abdullah, W Purnama, ABD Nandiyanto, MA Shafii
IOP Conference Series: Materials Science and Engineering 180 (1), 012079, 2017
42017
Analisis Densitas Nuklida Lead-Bismuth Cooled Fast Reactor (LFR) Bedasarkan Variasi Daya Keluaran
CR Guskha, MA Shafii, FH Irka, Z Su’ud
Jurnal Fisika Unand 5 (1), 7-13, 2016
42016
Analisis Laju Reaksi Neutron Dalam Sel Bahan Bakar Nuklir Pada Reaktor Cepat
R Martha, MA Shafii, A Afdal
Jurnal Ilmu Fisika 8 (2), 70-77, 2016
42016
Pola Penampang Lintang Makroskopik Total dalam Sel Bahan Bakar Nuklir
N Aini, MA Shafii, A Putra
Jurnal Ilmu Fisika 6 (1), 25-30, 2014
42014
Beberapa Metode Penyelesaian Persamaan Transport Neutron dalam Reaktor Nuklir Solution Methods of Neutron Transport Equation in Nuclear Reactors
MA Shafii
Jurnal Ilmu Dasar 14 (2), 59-65, 2013
42013
Effect of void-fraction on characteristics of several thorium fuel cycles in BWR
A Waris, MA Shafii, S Pramuditya, R Kurniadi, Z Su’ud
Energy conversion and management 63, 11-16, 2012
42012
Neutron Flux Interpolation with Finite Element Method in the Nuclear Fuel Cell Calculation using Collision Probability Method
MA Shafii, Z Su’ud, A Waris, N Kurniasih, M Ariani, Y Yulianti
AIP Conference Proceedings 1325 (1), 253-256, 2010
42010
Neutronic analysis of sodium‐cooled fast reactor design with different fuel types using modified CANDLE shuffling strategy in a radial direction
MA Shafii, R Septi, F Handayani Irka, A Arkundato, Z Su'ud
International Journal of Energy Research 45 (8), 12272-12283, 2021
32021
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