| 1 | Developing A Multi-criteria Decision-making Model For Nuclear Power Plant Location Selection Using Fuzzy Analytic Hierarchy Process And Fuzzy Vikor Methods Focused On Socio … | Cleaner Engineering and Technology 19, 100737, 2024 | 28 |
| 2 | Angle And Polarization-dependent Properties Of Non-concentric Silver Nanoring Plasmonic Resonance | AIP Conference Proceedings 3026 (1), 2024 | 1 |
| 3 | Calculation Of Neutron Flux Distribution And Diffusion Coefficient In The Slab Reactor Core Using Multi-group Diffusion Equation With Jacobi Method | AIP Conference Proceedings 3026 (1), 060004, 2024 | 0 |
| 4 | Pengayaan Materi Fisika Untuk Meningkatkan Pemahaman Siswa Terhadap Konsep Dinamika Rotasi Dan Keseimbangan Benda Tegar | INTEGRITAS: Jurnal Pengabdian 8 (1), 170-180, 2024 | 0 |
| 5 | Pengayaan Materi Pemanasan Global Di Sma Negeri 2 Gunung Talang Kabupaten Solok | BERNAS: Jurnal Pengabdian Kepada Masyarakat 5 (3), 1996-2002, 2024 | 1 |
| 6 | Two Decades Of Nuclear Energy Policy And Its Impact On Indonesia: A Bibliometric Review | Journal of Infrastructure, Policy and Development 8 (7), 4449, 2024 | 0 |
| 7 | Pengelolaan Laboratorium Bagi Guru-guru Fisika Dan Perancangan Laboratorium Percontohan Di Sman 2 Harau | BERNAS: Jurnal Pengabdian Kepada Masyarakat 4 (1), 69-77, 2023 | 5 |
| 8 | Multi-criteria Decision Making For Nuclear Power Plant Selection Using Fuzzy Ahp: Evidence From Indonesia | Energy and AI 14, 100263, 2023 | 50 |
| 9 | Sosialisasi Dan Pemetaan Potensi Tanah Longsor Menggunakan Metode Mikroseismik Dan Geolistrik Di Kawasan Objek Wisata Bukit Nobita | Jurnal Hilirisasi IPTEKS 6 (2), 132-142, 2023 | 3 |
| 10 | Effect Of Chromium Concentration Addition For Stabilizing The Crystal Structure Of Iron In Liquid Bismuth | AIP Conference Proceedings 2818 (1), 2023 | 0 |
| 11 | Perhitungan Shutdown Margin Teras Nuscale Menggunakan Openmc | Jurnal Fisika Unand 12 (4), 512-517, 2023 | 0 |
| 12 | Distribusi Dosis Radiasi Foton Berdasarkan Variasi Kedalaman Dan Luas Lapangan Penyinaran Pada Fantom Menggunakan Peawat Linac Tipe Clinac Cx | Jurnal Fisika Unand 11 (1), 89-96, 2022 | 1 |
| 13 | Diurnal Varian In Cloud Vertical Structure Over Sumatra From Radiosonde Observations During Cpea-i And Cpea-ii Campaigns | AIP Conference Proceedings 2391 (1), 2022 | 5 |
| 14 | Neutron Mean Free Path In The Slab Reactor Core Using One-dimensional Multi-group Diffusion Equation | Computational And Experimental Research In Materials And Renewable Energy 5Â …, 2022 | 1 |
| 15 | Rigid Procedure To Calculate The Melting Point Of Metal Using The Solid-liquid Phase (coexistence) Method | JURNAL ILMU FISIKA| UNIVERSITAS ANDALAS 14 (2), 132-140, 2022 | 0 |
| 16 | Neutron Flux Distribution Of Slab Reactor Core Using One-dimensional Multi-group Diffusion Equation In The Thermal Energy Region | AIP Conference Proceedings 2663 (1), 2022 | 1 |
| 17 | Effects Of Land Cover Change And Deforestation On Rainfall And Surface Temperature In New Capital City Of Indonesia | Jurnal Penelitian Pendidikan IPA 8 (6), 2849-2858, 2022 | 14 |
| 18 | Neutron Flux Distribution Of Slab Reactor Core Using One-dimensional Multi-group Diffusion Multi-group Diffusion Equation Inthe Thermal Energy Region | AIP Conference Proceedings, 2022 | 0 |
| 19 | Neutronic Analysis Of Sodium‐cooled Fast Reactor Design With Different Fuel Types Using Modified Candle Shuffling Strategy In A Radial Direction | International Journal of Energy Research 45 (8), 12272-12283, 2021 | 5 |
| 20 | Long-term Change In Characteristics Of Cloud Vertical Structures Over Sumatra From Radiosonde Observations | JURNAL ILMU FISIKA| UNIVERSITAS ANDALAS 13 (1), 41-53, 2021 | 3 |
| 21 | Characteristics Of Neutron Diffusion Coefficient As A Function Of Energy Group In The One-dimensional Multi-group Diffusion Equation Of Finite Slab Reactor Core | Journal of Physics: Conference Series 1869 (1), 012202, 2021 | 5 |
| 22 | Relationship Between Cloud Vertical Structures Inferred From Radiosonde Humidity Profiles And Precipitation Over Indonesia | Journal of Physics: Conference Series 1876 (1), 012011, 2021 | 0 |
| 23 | Study Of Neutronic Performance Of Sodium-cooled Fast Reactor Design For Various Output Power Using Radial Fuel Shuffling Strategy | Journal of Physics: Conference Series 1940 (1), 012031, 2021 | 0 |
| 24 | Analisis Perbandingan Nilai Conformity Index Dan Homogeneity Index Pada Teknik 3d-crt Dan Imrt Pada Kasus Kanker Payudara Berdasarkan Hasil Tps Di Rs Unand | Jurnal Fisika Unand 10 (4), 511-517, 2021 | 11 |
| 25 | Analisis Distribusi Fluks Neutron Pada Reaktor Berbentuk Slab Menggunakan Persamaan Difusi Multigrup Satu Dimensi Dengan Metode Gauss-seidel | Jurnal Fisika Unand 9 (3), 388-393, 2020 | 0 |
| 26 | Distribusi Dosis Radiasi Foton Berdasarkan Kedalaman Dan Luas Lapangan Penyinaran Pada Fantom Menggunakan Pesawat Linac Tipe Clinac Cx | - | 1 |
| 27 | Analisis Koefisien Difusi Neutron Terhadap Jarak Ekstrapolasi Dalam Persamaan Difusi Multigrup Satu Dimensi | Jurnal Fisika Unand 8 (4), 362-367, 2019 | 2 |
| 28 | Characteristics Of Rain Attenuation For Microwave-to-terahertz Waveband From Raindrop Size Distribution Observation In Indonesia | 2019 PhotonIcs & Electromagnetics Research Symposium-Spring (PIERS-Spring …, 2019 | 10 |
| 29 | Neutron Flux Distribution Calculation For Various Spatial Mesh Of Finite Slab Geometry Using One-dimensional Diffusion Equation | AIP Conference Proceedings 2180 (1), 2019 | 5 |
| 30 | Thermalhydraulic Performance Of Small Fast Reactor Base On Various Types Of Liquid Metal Coolant Materials | AIP Conference Proceedings 2180 (1), 2019 | 0 |
| 31 | The Pij Matrix And Flux Calculation Of One-dimensional Neutron Transport In The Slab Geometry Of Nuclear Fuel Cell Using Collision Probability Method | MATEC Web of Conferences 197, 02006, 2018 | 6 |
| 32 | Analisis Faktor Pelemahan Neutron Dari Berbagai Jenis Bahan Untuk Aplikasi Moderator/reflektor Dan Batang Kendali Pada Reaktor Termal | Jurnal Fisika Unand 7 (3), 208-214, 2018 | 0 |
| 33 | Analisis Kekritisan Sodium-cooled Fast Reactor (sfr) Berdasarkan Variasi Bahan Bakar | Jurnal Fisika Unand 7 (1), 69-72, 2018 | 1 |
| 34 | Analisis Kekritisan Lead-cooled Fast Reactor (lfr) Berdasarkan Variasi Bahan Bakar (u-zr Dan Un-pun) | Jurnal Fisika Unand 7 (1), 80-83, 2018 | 2 |
| 35 | Analisis Kekritisan Sodium-cooled Fast Reactor (sfr) Berdasarkan Variasi Daya Keluaran | Jurnal Fisika Unand 7 (1), 45-49, 2018 | 1 |
| 36 | Loss Of Load Probability Calculation For West Java Power System With Nuclear Power Plant Scenario | IOP Conference Series: Materials Science and Engineering 180 (1), 012079, 2017 | 4 |
| 37 | Neutron Distribution In The Nuclear Fuel Cell Using Collision Probability Method With Quadratic Flux Approach | IOP Conference Series: Materials Science and Engineering 180 (1), 012040, 2017 | 2 |
| 38 | Analysis Of Neutron Fission Reaction Rate In The Nuclear Fuel Cell Using Collision Probability Method With Non Flat Flux Approach | Journal of Physics: Conference Series 877 (1), 012013, 2017 | 6 |
| 39 | Perhitungan Matriks Pij Dan Distribusi Fluks Neutron Pada Sel Bahan Bakar Nuklir U-235 Dan U-238 Berbentuk Slab Menggunakan Moc | Jurnal Fisika Unand 6 (1), 74-80, 2017 | 3 |
| 40 | Analisis Densitas Nuklida Lead-bismuth Cooled Fast Reactor (lfr) Bedasarkan Variasi Daya Keluaran | Jurnal Fisika Unand 5 (1), 7-13, 2016 | 4 |
| 41 | Analisis Laju Reaksi Neutron Dalam Sel Bahan Bakar Nuklir Pada Reaktor Cepat | JURNAL ILMU FISIKA| UNIVERSITAS ANDALAS 8 (2), 70-77, 2016 | 4 |
| 42 | Uji Kemurnian Bensin Di Spbu Dan Pengecer Se-kota Padang Menggunakan Metode Spektroskopi Serapan Atom Merkuri | Jurnal Sainstek IAIN Batusangkar 2 (2), 143-149, 2016 | 0 |
| 43 | Perhitungan Penampang Lintang Mikroskopik Dalam Sel Bahan Bakar Nuklir | Spektra: Jurnal Fisika dan Aplikasinya 16 (1), 23-27, 2015 | 6 |
| 44 | Theoretical Analysis Of Integral Neutron Transport Equation Using Collision Probability Method With Quadratic Flux Approach | AIP Conference Proceedings 1615 (1), 91-95, 2014 | 3 |
| 45 | Study Of Iron Structure Stability In High Temperature Molten Lead-bismuth Eutectic With Oxygen Injection Using Molecular Dynamics Simulation | AIP Conference Proceedings 1615 (1), 156-161, 2014 | 4 |
| 46 | Pola Penampang Lintang Makroskopik Total Dalam Sel Bahan Bakar Nuklir | Jurnal Ilmu Fisika| Universitas Andalas 6 (1), 25-30, 2014 | 4 |
| 47 | Solution Methods Of Neutron Transport Equation In Nuclear Reactors | Jurnal Ilmu Dasar 14 (2), 59-65, 2013 | 3 |
| 48 | Beberapa Metode Penyelesaian Persamaan Transport Neutron Dalam Reaktor Nuklir Solution Methods Of Neutron Transport Equation In Nuclear Reactors | Jurnal Ilmu Dasar 14 (2), 59-65, 2013 | 5 |
| 49 | Nuclear Fuel Cell Calculation Using Collision Probability Method With Linear Non Flat Flux Approach | World Journal of Nuclear Science and Technology 2 (2), 49-53, 2012 | 13 |
| 50 | Effect Of Void-fraction On Characteristics Of Several Thorium Fuel Cycles In Bwr | Energy conversion and management 63, 11-16, 2012 | 4 |
| 51 | Preliminary Development Of Thermal Nuclear Cell Homogenization Code | AIP Conference Proceedings 1448 (1), 202-208, 2012 | 1 |
| 52 | Comparative Study On 233u And Plutonium Utilization In Molten Salt Reactor | Indonesian Journal of Physics 21 (3), 77-81, 2010 | 7 |
| 53 | Effect Of Fuel Fraction On Small Modified Candle Burn‐up Based Gas Cooled Fast Reactors | AIP Conference Proceedings 1325 (1), 249-252, 2010 | 7 |
| 54 | Neutron Flux Interpolation With Finite Element Method In The Nuclear Fuel Cell Calculation Using Collision Probability Method | AIP Conference Proceedings 1325 (1), 253-256, 2010 | 4 |
| 55 | Studi Awal Desain Reaktor Cepat Berpendingin Gas Berbasis Bahan Bakar Uranium Alam | Proceeding Seminar dan Workshop Nasional Pendidikan Teknik Elektro (SWNE), 93-98, 2010 | 9 |
| 56 | Analisis Kekritisan Teras Reaktor Nuklir Cepat Dan Termal Terkopel Berdasarkan Pada Letak Sumber Neutronnya | - | 0 |
| 57 | Analisis Termal Hidrolik Reaktor Spinnor Pada Kasus Kecelakaan Akibat Hilangnya Daya Pompa Pendingin | - | 0 |
| 58 | Fast Transient And Spatially Non‐homogenous Accident Analysis Of Two‐dimensional Cylindrical Nuclear Reactor | AIP Conference Proceedings 1325 (1), 245-248, 2010 | 0 |
| 59 | Fission Yield Calculation Method And Its Effect In Nuclear Fuel Cell Homogenization Calculation | Indonesian Journal of Physics 20 (2), 33-36, 2009 | 3 |
| 60 | Development Of Cell Homogenization Code Using General Geometry Approach | International Conference on Advances in Nuclear Science and Engineering in …, 2007 | 2 |
| 61 | Teori Indeks Bias Dan Sifat Termalnya Dalam Perambatan Gelombang Elektromagnet Yang Melewati Medium Isotrop Linear | Text | 0 |
| 62 | Disain Konseptual Sistem Keselamatan Pasif Pada Reaktor Cepat Berpendingin Timbal-bismut | - | 0 |
| 63 | Disain Konseptual Sistem Keselamatan Pasif Pada Reaktor Cepat Berpendingin Timbal-bismut | - | 0 |
| 64 | Energy And Ai | - | 0 |
| 65 | Calculation Of Collision Probability Matrix Of Nuclear Fuel Cell As A Function Of Neutron Energy Group Using Flat Flux Model | - | 0 |
| 66 | Pengelolaan Laboratorium Di Sman 2 Sipora Kepulauan Mentawai | Jurnal Pengabdian kepada Masyarakat Nusantara 6 (2), 2025 | 0 |
| 67 | The Social Factors Considered In Site Selection For Nuclear Power Plants: A Case Study Of Borneo Island, Indonesia | Progress in Nuclear Energy 180, 105626, 2025 | 0 |
| 68 | Prioritizing Safety Aspects: Advanced Multi-criteria Decision-making For Nuclear Power Plant Site Selection In Indonesia. | Journal of Sustainable Development of Energy, Water & Environment Systems …, 2024 | 1 |
