Pendidikan	Sarjana Pendidikan, Universitas Negeri Semarang, Indonesia, 2010 Magister Sains, Institut Teknologi Bandung, Indonesia, 2014 Doktor, INSTITUT TEKNOLOGI BANDUNG, INDONESIA, 2018
Interes Riset	Riset dalam bidang reaktor niklir, Pembangkit Listrik Tenaga Nuklir (PLTN), PWR, GFR, MSR
Metode Penelitian	SRAC, SRAC-COREBN, OpenMC
Topik Riset	Komputasi Desain Reaktor Nuklir, PLTN, Reaktor Cepat, Reaktor Thermal, GFR, PWR, MSR
Software	SRAC, SRAC-COREBN, OpenMC. Origin
Sistem Operasi	Limux Ubuntu, Windows
Link Publikasi	Scopus, Sinta, Google Schoolar, WOS
Publikasi	Molecular dynamics simulation of corrosion and its inhibition: comparison of structural stability of Fe/FeNi/FeNiCr/FeNiCrTi steels under high-temperature liquid lead EUREKA : Physics and Engineering, 151-163 Neutronics analysis of UN-PuN fuel for 300MW pressurized water reactor using SRAC-COREBN code EUREKA : Physics and Engineering, 12-23 NEUTRONIC ANALYSIS ON MOLTEN SALT REACTOR FUJI-12 USING 235U AS FISSILE MATERIAL IN LiF-BeF2-UF4 FUEL Eastern-European Journal of Enterprise Technologies 5, 6-12 Preface: The 3rd International Conference on Physical Instrumentation and Advanced Materials (ICPIAM) 2021 AIP Conference Proceedings 2663 (1), 010001 Preliminary study of 300 MWth pressurized water reactor with carbide fuel with addition neptunium 237 using SRAC-COREBN code AIP Conference Proceedings 2663 (1), 070006 The potential use of a hybrid human-detector for physical distance monitoring AIP Conference Proceedings 2663 (1), 040002 GPVDM simulation of thickness effect on power conversion efficiency of PEDOT: PSS/P3HT: PCBM solar cell performance AIP Conference Proceedings 2663 (1), 070002 Lennard-Jones and Morse potential comparison for studying the liquid lead corrosion AIP Conference Proceedings 2663 (1), 030002 Rigid Procedure to Calculate the Melting Point of Metal Using the Solid-Liquid Phase (Coexistence) Method Jurnal Ilmu Fisika 14 (2), 132-140 TRASH CAN-COMPOSTER: ALAT PENCACAH SAMPAH ORGANIK UNTUK PENCACAH SAMPAH LIMBAH PERTANIAN JMM (Jurnal Masyarakat Mandiri) 6 (3), 1712-1721 Studi Desain Boiling Water Reactor (BWR) Berdaya 100MWt Berbahan Bakar Thorium Karbida POSITRON 12 (1), 9-17 Comparison of Thorium Nitride and Uranium Nitride Fuel on Small Modular Pressurized Water Reactor in Neutronic Analysis Using SRAC Code Eastern-European Journal of Enterprise Technologies 2 (8), 116 Simulation of Hydrogenated Amorphous Silicon-based Solar Cell: Investigation of JV Characteristic in Optimum Thickness Journal of Physics: Conference Series 1951 (1), 012028 Analisis fraksi volume bahan bakar uranium karbida pada reaktor cepat berpendingin gas menggunakan srac code Jurnal Jaring SainTek 3 (1), 13-18 Phase Transition of Fe₃O₄ Magnetic Material Based on Observation of Curie Temperature and Hysteresis Curve: Micromagnetic Simulation Study European Journal of Applied Physics 3 (2), 3-10 Comparative study on various thermal power for gas cooled fast reactor with uranium plutonium nitride fuel AIP Conference Proceedings 2278 (1), 020040 Actinide Minor Addition on Uranium Plutonium Nitride Fuel for Modular Gas Cooled Fast Reactor Journal of Physics: Conference Series 1493 (1), 012020 Neutronic analysis of comparation UN-PuN fuel and ThN fuel for 300MWth Gas Cooled Fast Reactor long life without refueling Journal of Physics: Conference Series 1436 (1), 012132 Study of Neptunium, Americium and Protactinium Addition for 300MWth GFR with Uranium Carbide Fuel Computational And Experimental Research In Materials And Renewable Energy 2 Performance of Thorium Uranium Nitride (Th, U233) N Fuel for 500 MWth GFR Long-Life Without Refuelling use FIITB-CHI Code Journal of Physics: Conference Series 1204 (1), 012127 Studi Karakteristik Aliran Gas Berbagai Polutan Menggunakan Simulasi CFD (Computational Fluid Dynamics) Seminar Nasional Fisika dan Pembelajarannya, 184-191 Analysis of Tensile Strenght and Shear Modulus of GRE Pipe using Ansys Computational And Experimental Research In Materials And Renewable Energy 1 Design Study of 600 MWt Long Life Modular Gas Cooled Fast Reactors Journal of Physics: Conference Series 1090 (1), 012021 Neutronic Analysis of UN-PuN Fuel use FI-ITB-CHI Code for 500MWth GFR Long Life Without Refueling Journal of Physics: Conference Series 1090 (1), 012033 Comparison of uranium plutonium nitride (U‐Pu‐N) and thorium nitride (Th‐N) fuel for 500 MWth gas‐cooled fast reactor (GFR) long life without refueling International Journal of Energy Research 42 (1), 214-220 WITHDRAWN: Comparison of uranium plutonium nitride (UPuN) and thorium nitride (ThN) fuel for 500 MWth Gas Cooled Fast Reactor (GFR) longlife without refueling International Journal of Hydrogen Energy Comparative Study on Various Geometrical Core Design of 300 MWth Gas Cooled Fast Reactor with UN-PuN Fuel Longlife without Refuelling Journal of Physics: Conference Series 877 (1), 012064 Fuel Fraction Analysis of 500 MWth Gas Cooled Fast Reactor with Nitride (UN-PuN) Fuel without Refueling Journal of Physics: Conference Series 799 (1), 012022 Neutronic analysis of thorium nitride (Th, U233) N fuel for 500MWth gas cooled fast reactor (GFR) long life without refueling Key Engineering Materials 733, 47-50 The prospect of uranium nitride (UN-PuN) fuel for 25-100MWe gas cooled fast reactor long life without refuelling Journal of Physics: Conference Series 776 (1), 012103 Design Study of 200MWth Gas Cooled Fast Reactor with Nitride (UN-PuN) Fuel Long Life without Refueling MATEC Web of Conferences 82, 03008 The prospect of uranium nitride (UN) and mixed nitride fuel (UN-PuN) for pressurized water reactor AIP Conference Proceedings 1677 (1), 120005 Perhitungan Neutronik Teras Homogen dari High Temperature Gas Cooled Reactor (HTGR) dengan Bahan Bakar Uranium Nitrida RD Syarifah, IR Maemunah, Z Su’ud