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Author

Muhammad Ilham

ORCID: 0009-0002-1973-4269
Observed ORCID: 0009-0002-1973-4269
OpenAlex ID: A5113946204
Fuel Assembly Design Study for Modular Gas Cooled Fast Reactor using Monte Carlo Parallelization Method
2021 · Muhammad Ilham, Helen Raflis, et al. · Journal of Physics Conference Series · 5
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A Simple Analytical Model to Predict the Freeze Plug Opening Time in Molten Salt Reactors
2023 · Muhammad Ilham, Tomio Okawa · Journal of Nuclear Engineering and Radiation Science · 4
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WITHDRAWN: Comparison of uranium plutonium nitride (U Pu N) and thorium nitride (Th N) fuel for 500 MWth Gas Cooled Fast Reactor (GFR) longlife without refueling
2017 · Ratna Dewi Syarifah, Zaki Su'ud, et al. · International Journal of Hydrogen Energy · 4
Numerical Analysis of Simple Heat Equation to Predict the Opening Time of the Freeze Plug in Molten Salt Reactors
2022 · Muhammad Ilham, Tomio Okawa · The Proceedings of the International Conference on Nuclear Engineering (ICONE) · 2
Analisa Sifat Mekanik Material Komposit Serat Kulit Durian Matriks Polimer
2014 · Muhammad Ilham, Burmawi, et al. · ABSTRACT OF UNDERGRADUATE RESEARCH, FACULTY OF INDUSTRIAL TECHNOLOGY, BUNG HATTA UNIVERSITY · 2
Development of Linkage Program Code OpenMC and ORIGEN2.2 for Neutronic Analysis and Burnup Nuclear Reactor Program
2022 · Muhammad Ilham, Helen Raflis, et al. · Journal of Physics Conference Series · 1
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Numerical Investigation of Safety System Parameters in Molten Salt Reactor: Wall Effect on Freeze Valve Opening Time
2021 · Muhammad Ilham, Indarta Kuncoro Aji, et al. · The Proceedings of the International Conference on Nuclear Engineering (ICONE) · 1
Moving Particle Semi-implicit Method in Simulating Water-Oil Penetration
2019 · Y Yulianto, Asril PA Mustari, et al. · Indonesian Journal of Physics · 1
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Design Study of Modular Nuclear Power Plant with Small Long Life Gas Cooled Fast Reactors Utilizing MOX Fuel
2017 · Muhammad Ilham, Zaki Su’ud · Journal of Physics Conference Series · 1
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Improved core performance through neutronic parameter optimization in a 300 MWTH UN-PuN fueled Gas-cooled Fast Reactor
2026 · Ratna Dewi Syarifah, Fajri Prasetya, et al. · Eastern-European Journal of Enterprise Technologies
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Numerical study on the effects of tube inclination angle and heat conductive cover plate on freeze plug performance in molten salt reactors
2024 · Muhammad Ilham, Indarta Kuncoro Aji, et al. · Nuclear Engineering and Design
Utilisation of Plastic Sacks Fibre and Bran Ash for Soft Clay Shear Strength
2016 · Nyimas Septi Rika Putri, Ratna Dewi, et al. · Jurnal Teknologi
Works count: 12
Citation count: 21
H-index: 3
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