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KHAIRUL BASAR

Institut Teknologi Bandung S3 - Rekayasa Nuklir SINTA ID : 6037145
1.437
SINTA Score Overall
29
SINTA Score 3Yr
1.437
Affil Score
29
Affil Score 3Yr
Latest number of publications
  Scopus Analysis  

Predicting Melting Temperatures of Freeze Valve in Molten Salt Reactors using LSTM-Based Deep Learning Models
Q3 as Conference Proceedin Journal of Physics Conference Series
Author Order : 2 of 4     Creator : Riupassa R.D.
2024 1 cited
Numerical Investigation of Freeze Valve Melting Behavior in Molten Salt Reactor using OpenFOAM
Q4 as Conference Proceedin Journal of Physics Conference Series
Author Order : 2 of 4     Creator : Riupassa R.D.
2022 0 cited
Study of Steady State Heat Conduction in Composite Layer by Linear Triangular Finite Element
Q4 as Conference Proceedin Journal of Physics Conference Series
Author Order : 4 of 6     Creator : Riupassa R.D.
2021 0 cited
Actinide Minor Addition on Uranium Plutonium Nitride Fuel for Modular Gas Cooled Fast Reactor
Q4 as Conference Proceedin Journal of Physics Conference Series
Author Order : 3 of 4     Creator : Syarifah R.D.
2020 4 cited
Performance of Thorium Uranium Nitride (Th, U233)N Fuel for 500 MWth GFR Long-Life Without Refuelling use FIITB-CHI Code
Q4 as Conference Proceedin Journal of Physics Conference Series
Author Order : 3 of 4     Creator : Syarifah R.D.
2019 0 cited
Preliminary study of bamboo-like tree structure based on granular particle-spring model: Relaxation and tortuosity
Q4 as Conference Proceedin Journal of Physics Conference Series
Author Order : 5 of 6     Creator : Viridi S.
2019 0 cited
Advanced Nuclear Reactor AP1000 with ThO2-UO2 Fuel
Q4 as Conference Proceedin Journal of Physics Conference Series
Author Order : 4 of 6     Creator : Baskara R.F.
2019 1 cited
PREFACE: The 6th International Conference on Mathematics and Natural Sciences
Q4 as Conference Proceedin Journal of Physics Conference Series
Author Order : 2 of 5     Creator : Natalia D.
2019 0 cited
Neutronic Analysis of UN-PuN Fuel use FI-ITB-CHI Code for 500MWth GFR Long Life Without Refueling
Q4 as Conference Proceedin Journal of Physics Conference Series
Author Order : 3 of 4     Creator : Syarifah R.D.
2018 4 cited
Comparison of uranium plutonium nitride (U-Pu-N) and thorium nitride (Th-N) fuel for 500 MWth gas-cooled fast reactor (GFR) long life without refueling
Q1 as Journal International Journal of Energy Research
Author Order : 3 of 6     Creator : Syarifah R.D.
2018 15 cited
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Summary

Article Quartile
Research Output
  Scopus GScholar WOS
Article 47 75 35
Citation 257 398 150
Cited Document 31 44 25
H-Index 11 12 7
i10-Index 11 16 6
G-Index 1 1 1
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