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DWI IRWANTO

Institut Teknologi Bandung S2 - Ilmu Dan Rekayasa Nuklir SINTA ID : 5972749
2.504
SINTA Score Overall
408
SINTA Score 3Yr
2.504
Affil Score
408
Affil Score 3Yr
Latest number of Publication and Citations
Optimization of uranium and uranium-thorium fuel utilization in pebble bed for PeLUIt-10 reactor using PEBBED code
Authors : C Wulandari, D Irwanto, N Widiawati, N Trianti, F Miftasani, T Setiadipura, ... Nuclear Engineering and Design 433, 113873, 2025
2025 0 cited
Electricity Theft Detection Using Machine Learning in Traditional Meter Postpaid Residential Customers: A Case Study on State Electricity Company (PLN) Indonesia
Authors : AP Taruna, G Arisona, D Irwanto, AB Bestari, W Juniawan IEEE Access, 2025
2025 0 cited
Classification Based on the Support Vector Machine for Determining Operational Targets for Controlling Electricity Usage with Conventional Meters: A Case Study of Industrial …
Authors : G Arisona, AP Taruna, D Irwanto, AB Bestari, W Juniawan IEEE Access, 2025
2025 0 cited
Effective Multiplication Factor Analysis of Gas-cooled Reactor using OpenMC code with ENDF/B-VII. 1, ENDF/B-VIII. 0 and JENDL-5.0 Nuclear Data
Authors : MAI Rachmat, D Irwanto Journal of Physics: Conference Series 2734 (1), 012056, 2024
2024 1 cited
Computational analysis for predicting fission product release of PeLUIt-40 under normal operating conditions
Authors : A Purwaningsih, D Irwanto, JH Purba Nuclear Engineering and Design 430, 113677, 2024
2024 0 cited
Design study of gas-cooled fast reactor with natural uranium as fuel employing modified CANDLE shuffling strategy in the axial direction
Authors : JP Ndayiragije, Z Su’ud, A Waris, D Irwanto Kerntechnik 89 (5), 595-605, 2024
2024 0 cited
3-Dimensional full core neutronic analysis for uranium nitride fuel CANDLE reactor using Monte Carlo MCNP6 code
Authors : M Afifah, Z Su’ud, N Trianti, D Irwanto Nuclear Engineering and Design 425, 113340, 2024
2024 1 cited
Investigating geometry adjustments for enhanced performance in a PeLUIt-10 MWt pebble bed HTGR with OTTO refueling scheme
Authors : F Miftasani, RAP Dwijayanto, G Abrar, N Widiawati, N Trianti, ... Nuclear Engineering and Design 422, 113163, 2024
2024 4 cited
Comparison of Neutronic Analysis for 250 MWth Molten Salt Reactor using Monte Carlo OpenMC Code with Different Nuclear Data Libraries of JENDL 5.0, ENDF/B-VII. 1, ENDF/B-VIII …
Authors : M Variastuti, D Irwanto Journal of Physics: Conference Series 2866 (1), 012085, 2024
2024 0 cited
Effect of Different Temperature and Nuclear Data Libraries in Criticality Calculations of 300 MWt Molten Salt Reactor
Authors : M Variastuti, D Irwanto Journal of Physics: Conference Series 2734 (1), 012055, 2024
2024 1 cited
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Summary

Article Quartile
Research Output
  Scopus GScholar WOS
Article 90 123 48
Citation 363 528 155
Cited Document 62 73 34
H-Index 11 13 6
i10-Index 13 16 4
G-Index 1 1 3
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