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DWI IRWANTO

Institut Teknologi Bandung S2 - Ilmu Dan Rekayasa Nuklir SINTA ID : 5972749
2.363
SINTA Score Overall
643
SINTA Score 3Yr
0
Affil Score
0
Affil Score 3Yr
Latest number of publications
  Scopus Analysis  

3-Dimensional full core neutronic analysis for uranium nitride fuel CANDLE reactor using Monte Carlo MCNP6 code
Q2 Journal Nuclear Engineering and Design
Author Order : 4 of 4     Creator : Afifah M.
2024 0 cited
Effect of Different Temperature and Nuclear Data Libraries in Criticality Calculations of 300 MWt Molten Salt Reactor
Q3 Journal 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 Journal Journal of Physics: Conference Series
Author Order : 2 of 2     Creator : Rachmat M.A.I.
2024 0 cited
Investigating geometry adjustments for enhanced performance in a PeLUIt-10 MWt pebble bed HTGR with OTTO refueling scheme
Q2 Journal Nuclear Engineering and Design
Author Order : 7 of 9     Creator : Miftasani F.
2024 1 cited
Comparative analysis on small modular reactor (SMR) with uranium and thorium fuel cycle
Q2 Journal Nuclear Engineering and Design
Author Order : 3 of 4     Creator : Amatullah A.
2024 1 cited
Experimental study of solid low-density tilted plate's erosion by low melting temperature molten materials
Q4 Journal AIP Conference Proceedings
Author Order : 4 of 4     Creator : Hidayati A.N.
2023 0 cited
Optimization of Core Regions and Fuel Fractions for Better Power Peaking Factor of 150, 450 and 1,000 MWth Molten Salt Reactor
Q3 Journal Trends in Sciences
Author Order : 2 of 4     Creator : Variastuti M.
2023 0 cited
Design study of small modular gas-cooled fast reactor employing modified CANDLE burnup with radial direction shuffling scheme
Q3 Journal Kerntechnik
Author Order : 3 of 5     Creator : Irka F.H.
2023 1 cited
Comparison of thermal-hydraulic calculation in 100 MWt thorium-based HTGR using SiC and ZrC TRISO coated fuel particle
Q2 Journal Nuclear Engineering and Design
Author Order : 7 of 9     Creator : Miftasani F.
2023 3 cited
Experimental and numerical analysis of impingement temperature effect on the sacrificial plate's hole formation during nuclear severe accident
Q1 Journal Progress in Nuclear Energy
Author Order : 3 of 4     Creator : Hidayati A.N.
2023 0 cited
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Summary

Article Quartile
Research Output
  Scopus GScholar WOS
Article 84 114 46
Citation 302 455 130
Cited Document 58 69 31
H-Index 10 12 6
i10-Index 10 15 4
G-Index 1 1 1
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