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DWI IRWANTO

Institut Teknologi Bandung S2 - Ilmu Dan Rekayasa Nuklir SINTA ID : 5972749
2.615
SINTA Score Overall
360
SINTA Score 3Yr
2.615
Affil Score
360
Affil Score 3Yr
Latest number of publications
  Scopus Analysis  

Neutronic performance of natural uranium-thorium composite fuels on gas-cooled fast reactor employing modified CANDLE burn-up strategy
Q2 as Journal International Journal of Global Energy Issues
Author Order : 4 of 4     Creator : Ndayiragije J.P.
2026 0 cited
Optimization of uranium and uranium-thorium fuel utilization in pebble bed for PeLUIt-10 reactor using PEBBED code
Q2 as Journal Nuclear Engineering and Design
Author Order : 2 of 7     Creator : Wulandari C.
2025 3 cited
Investigating the soil surface properties behind elevated natural radiation in Mamuju, Indonesia
Q1 as Journal Scientific Reports
Author Order : 5 of 15     Creator : Abdullah A.R.A.
2025 2 cited
Safety margin evaluation of RSG-GAS during LOFA considering ageing-induced degradation of coast-down flow and recent decay heat measurement
Q2 as Journal Nuclear Engineering and Design
Author Order : 5 of 6     Creator : Hastuti E.P.
2025 0 cited
Electricity Theft Detection Using Machine Learning in Traditional Meter Postpaid Residential Customers: A Case Study on State Electricity Company (PLN) Indonesia
Q1 as Journal IEEE Access
Author Order : 3 of 5     Creator : Taruna A.P.
2025 5 cited
Classification Based on the Support Vector Machine for Determining Operational Targets for Controlling Electricity Usage With Conventional Meters: A Case Study of Industrial and Business Tariff Customers From PT PLN (Persero) Indonesia
Q1 as Journal IEEE Access
Author Order : 3 of 5     Creator : Arisona G.
2025 0 cited
Effect of Different Temperature and Nuclear Data Libraries in Criticality Calculations of 300 MWt Molten Salt Reactor
Q3 as Conference Proceedin Journal of Physics Conference Series
Author Order : 2 of 2     Creator : Variastuti M.
2024 1 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.0, and JEFF 3.3
Q3 as Conference Proceedin Journal of Physics Conference Series
Author Order : 2 of 2     Creator : Variastuti M.
2024 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
Q3 as Conference Proceedin Journal of Physics Conference Series
Author Order : 2 of 2     Creator : Rachmat M.A.I.
2024 1 cited
Computational analysis for predicting fission product release of PeLUIt-40 under normal operating conditions
Q2 as Journal Nuclear Engineering and Design
Author Order : 2 of 3     Creator : Purwaningsih A.
2024 1 cited
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Summary

Article Quartile
Research Output
  Scopus GScholar WOS
Article 93 137 48
Citation 428 644 155
Cited Document 67 86 34
H-Index 12 14 6
i10-Index 17 27 4
G-Index 1 2 3
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