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[vc_empty_space][vc_btn title=”Lihat Profil Scopus” style=”gradient-custom” gradient_custom_color_1=”#00316d” gradient_custom_color_2=”#2071ea” size=”sm” align=”center” css_animation=”bounceInDown” link=”url:https%3A%2F%2Fwww.scopus.com%2Fauthid%2Fdetail.uri%3FauthorId%3D36125036700||target:%20_blank|”][/vc_column_inner][/vc_row_inner][vc_row_inner css=”.vc_custom_1624510077690{border-right-width: 1px !important;padding-top: 32px !important;border-right-color: #b2b2b2 !important;border-right-style: solid !important;border-radius: 1px !important;}”][/vc_row_inner][/vc_column][vc_column width=”2/3″][vc_row_inner][vc_column_inner css=”.vc_custom_1624509956940{border-left-width: 1px !important;border-left-color: #969696 !important;border-left-style: solid !important;border-radius: 1px !important;}”][megatron_heading title=”Dwi Irwanto” size=”size-md” sub_title=”FMIPA” text_align=”text-left”][vc_separator][/vc_column_inner][/vc_row_inner][vc_column_text]Energy Engineering and Power Technology • Fuel Technology • Renewable Energy, Sustainability and the Environment • Condensed Matter Physics • Electrical and Electronic Engineering • Mechanical Engineering • Mechanics of Materials • Nuclear Energy and Engineering • Applied Mathematics • Artificial Intelligence • Nuclear and High Energy Physics • Radiology, Nuclear Medicine and Imaging • Computational Mathematics • Modeling and Simulation • Safety, Risk, Reliability and Quality • Waste Management and Disposal • Radiation • Materials Science (all) • Engineering (all) • Physics and Astronomy (all) • Chemistry (all)[/vc_column_text][/vc_column][/vc_row][vc_row layout=”boxed” css=”.vc_custom_1624522217430{margin-top: 20px !important;}”][vc_column][vc_tta_tabs style=”classic” color=”blue” spacing=”5″ active_section=”1″ no_fill_content_area=”true”][vc_tta_section i_type=”fontawesome” i_icon_fontawesome=”fa fa-book” add_icon=”true” title=”Karya” tab_id=”karya”][vc_empty_space height=”20px”][vc_column_text]
Preliminary Study of 20 MWth Experiment Power Reactor based on Pebble Bed Reactor
Dwi Irwanto,Sidik Permana,Syeilendra Pramuditya
Journal of Physics: Conference Series vol:877, issue:012058, page:1-
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Comparison of Several Thermal Conductivity Constants for Thermal Hydraulic Calculation of Pebble Bed Reactor
Dwi Irwanto,Asril Pramutadi,Topan Setiadipura
Journal of Physics: Conference Series vol:877, issue:012031, page:1-
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Preliminary Design Study of Small Power 30-50 MWt Experiment Power Reactor based on High Temperature Pebble Bed Gas Cooled Reactor Technology
Dwi Irwanto,Sidik Permana,Asril Pramutadi,Syeilendra Pramuditya
Journal of Physics: Conference Series vol:1127, issue:012024, page:1-
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Simulation of mechanical stress on stainless steel for Pb-Bi corrosion test by using ABAQUS
D. Irwanto,A.P.A. Mustari,B.A. Budiman
IOP Conference Series: Materials Science and Engineering vol:180, issue:012009, page:1-
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Preliminary neutronic study on pu-based OTTO cycle pebble bed reactor
T. Setiadipura,D. Irwanto,None Zuhair
Kerntechnik vol:82, issue:124.110793, page:1-647
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Comparative analysis on nuclear fuel sustainability aspect of FBR
Sidik Permana,Dwi Irwanto,Mitsutoshi Suzuki,Masaki Saito
Journal of Physics: Conference Series vol:799, issue:012006, page:1-
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High temperature corrosion of cold worked YUS409D bellows of bellow-sealed valve in LBE
A.P.A. Mustari,D. Irwanto,M. Takahashi
Journal of Physics: Conference Series vol:795, issue:012005, page:1-
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Melting Penetration Simulation of Fe-U System at High Temperature Using MPS-LER
A.P.A. Mustari,Dwi Irwanto,A. Yamaji
Journal of Physics: Conference Series vol:739, issue:012016, page:1-
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Study on the Effects of Enrichment and Fraction of Coated Fuel Particles on Fissile Utilization of 100 MWt Prismatic-type of High Temperature Gas Reactor
Ayu Lia Pratama,Dwi Irwanto
Journal of Physics: Conference Series vol:1493, issue:012027, page:1-
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Enhancing the performance of a long-life modified CANDLE fast reactor by using an enriched 208Pb as coolant
Nina Widiawati,Zaki Su’ud,Dwi Irwanto,Sidik Permana,Naoyuki Takaki,Hiroshi Sekimoto
Nuclear Engineering and Technology vol:53, issue:j.net.2020.07.008, page:1-429
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Neutronic Aspect Assessment on the use of ZrC Triso-Coated Particle (TRIZO) in a High-Temperature Gas-cooled Reactor (HTGR)
Fitria Miftasani,Zaki Su’ud,Dwi Irwanto
Journal of Physics: Conference Series vol:1493, issue:012029, page:1-
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Neutronic Analysis of Lead208-Bismuth Eutectic-Cooled Modified CANDLE Reactor with Core Geometry Variations
Nina Widiawati,Zaki Su’ud,Dwi Irwanto,Sidik Permana,Hiroshi Sekimoto
Journal of Physics: Conference Series vol:1493, issue:012010, page:1-
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HTTR 30MWth Reactor with Homogenous (Th,U)O2 Fuel
Anni Nuril Hidayati,Abdul Waris,Dwi Irwanto,Asril Pramutadi
Journal of Physics: Conference Series vol:1204, issue:012134, page:1-
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Homogenous (Th,Pu)O2 Fuel Utilization on High Temperature Test Reactor 30MWt
Anni Nuril Hidayati,Abdul Waris,Dwi Irwanto,Asril Pramutadi
Journal of Physics: Conference Series vol:1204, issue:012133, page:1-
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Comparative Analysis on Fuel Breeding for Less Moderation Ratio of Water Cooled Reactor
Sidik Permana Asril Pramutadi,Syeilendra Pramuditya,Dwi Irwanto
Journal of Physics: Conference Series vol:1204, issue:012129, page:1-
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Fuel Breeding Analysis on Low Moderated Fuel Ratio Based on Actinides Closed Water-Cooled Thorium Reactor
Sidik Permana,Syeilendra Pramuditya,Dwi Irwanto
Journal of Physics: Conference Series vol:1090, issue:012061, page:1-
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Neutronic Comparison Study between Pb(208)-Bi and Pb(208) as a Coolant in the Fast Reactor with Modified CANDLE Burn up Scheme.
Nina Widiawati,Zaki Suud,Dwi Irwanto,Hiroshi Sekimoto
Journal of Physics: Conference Series vol:1090, issue:012071, page:1-
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Charged particle flow base on mesoscale simulation with coupling MPCD-MD method in two dimension channel
Annas Nasrudin,Sparisoma Viridi,Dwi Irwanto
Journal of Physics: Conference Series vol:799, issue:012011, page:1-
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Prediction of melting penetration of Armco iron by liquid uranium using MPS-LER
A.P.A. Mustari,None Syeilendra,Dwi Irwanto,N.A. Aprianti,None Iksal,None Sumiati
Journal of Physics: Conference Series vol:799, issue:012019, page:1-
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Comparative studies on plutonium utilization in HTTR with helium and carbon dioxide gas coolants
Abdul Waris,Syeilendra Pramuditya,Dwi Irwanto,Puguh Andik Prastyo,Hiroshi Sekimoto
International Journal of Hydrogen Energy vol:41, issue:j.ijhydene.2016.02.117, page:1-6989
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Preliminary neutronic design of high burnup OTTO cycle pebble bed reactor
T. Setiadipura,None Zuhair,D. Irwanto
Atom Indonesia vol:41, issue:aij.2015.350, page:1-15
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Comparative Studies on UO2 Fueled HTTR Several Nuclear Data Libraries
Anni N. Hidayati,Puguh A. Prastyo,Abdul Waris,Dwi Irwanto
Journal of Physics: Conference Series vol:877, issue:012049, page:1-
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Neutronic Study of Small Modular Reactor Thorium Based as A Model of Nuclear Power Plant for Remote Area
Muhamad Irfan,Romie Oktovianus Bura,Zaki Su’Ud,Dwi Irwanto
2018 2nd Borneo International Conference on Applied Mathematics and Engineering, BICAME 2018 vol:, issue:BICAME45512.2018.1570505679, page:1-312
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Performance of Thorium Uranium Nitride (Th, U233)N Fuel for 500 MWth GFR Long-Life Without Refuelling use FIITB-CHI Code
Ratna Dewi Syarifah,Zaki Su’ud,Khairul Basar,Dwi Irwanto
Journal of Physics: Conference Series vol:1204, issue:012127, page:1-
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Fuel fraction analysis of 500 MWth gas cooled fast reactor with nitride (UN-PuN) fuel without refueling
Ratna Dewi Syarifah,Zaki Su’ud,Khairul Basar,Dwi Irwanto
Journal of Physics: Conference Series vol:799, issue:012022, page:1-
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Delayed neutrons effect on power reactor with variation of fluid fuel velocity at MSR Fuji-12
Indarta Kuncoro Aji,Syeilendra Pramuditya,None Novitrian,Dwi Irwanto,Abdul Waris
Journal of Physics: Conference Series vol:799, issue:012004, page:1-
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Preliminary Study on LiF4-ThF4-PuF4 Utilization as Fuel Salt of miniFUJI Molten Salt Reactor
Abdul Waris,Syeilendra Pramuditya,None Widayani,Dwi Irwanto,Indarta K. Aji
Journal of Physics: Conference Series vol:739, issue:012004, page:1-
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Actinide Minor Addition on Uranium Plutonium Nitride Fuel for Modular Gas Cooled Fast Reactor
Ratna Dewi Syarifah,Zaki Su’ud,Khairul Basar,Dwi Irwanto
Journal of Physics: Conference Series vol:1493, issue:012020, page:1-
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The prediction of helium gas viscosity under high pressure and high temperature with the Chapman-Enskog solution and excess viscosity
Elin Yusibani,Yasuyuki Takata,Zaki Suud,Dwi Irwanto
Journal of Physics: Conference Series vol:799, issue:012008, page:1-
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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
Ratna Dewi Syarifah,Zaki Su’ud,Khairul Basar,Dwi Irwanto,Sandro Clief Pattipawaej,Muhammad Ilham
International Journal of Energy Research vol:42, issue:er.3923, page:1-220
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Neutronic Analysis of UN-PuN Fuel use FI-ITB-CHI Code for 500MWth GFR Long Life Without Refueling
Ratna Dewi Syarifah,Zaki Su’Ud,Khairul Basar,Dwi Irwanto
Journal of Physics: Conference Series vol:1090, issue:012033, page:1-
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Comparative Study on Various Geometrical Core Design of 300 MWth Gas Cooled Fast Reactor with UN-PuN Fuel Longlife without Refuelling
Ratna Dewi Syarifah,Zaki Su’Ud,Khairul Basar,Dwi Irwanto
Journal of Physics: Conference Series vol:877, issue:012064, page:1-
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Comparative Evaluation on Several Reactor Type of Actinide Closed-Cycle Schemes
Sidik Permana,Asril Pramutadi,Syeilendra Pramuditya,Dwi Irwanto
Journal of Physics: Conference Series vol:1090, issue:012011, page:1-
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The prospect of uranium nitride (UN-PuN) fuel for 25- 100MWe gas cooled fast reactor long life without refuelling
R.D. Syarifah,Z. Su’Ud,K. Basar,D. Irwanto
Journal of Physics: Conference Series vol:776, issue:012103, page:1-
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Reflector materials selection for core design of modular gas-cooled fast reactor using OpenMC code
Helen Raflis,Ilham Muhammad,Zaki Su’ud,Abdul Waris,Dwi Irwanto
International Journal of Energy Research vol:, issue:er.6042, page:1-
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Neutronic Analysis of Modular Gas-cooled Fast Reactor for 5-25% of Plutonium Fuel using Parallelization MCNP6 Code
Helen Raflis,M. Ilham,Zaki Su’ud,Abdul Waris,Dwi Irwanto
Journal of Physics: Conference Series vol:1493, issue:012008, page:1-
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Neutronic analysis of Thorium Nitride (Th, U233)N fuel for 500MWth Gas Cooled Fast Reactor (GFR) long life without refueling
Ratna Dewi Syarifah,Yacobus Yulianto,Zaki Su’ud,Khairul Basar,Dwi Irwanto
Key Engineering Materials vol:733 KEM, issue:KEM.733.47, page:1-50
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Design Study of 200MWth Gas Cooled Fast Reactor with Nitride (UN-PuN) Fuel Long Life without Refueling
Ratna Dewi Syarifah,Yacobus Yulianto,Zaki Su’ud,Khairul Basar,Dwi Irwanto
MATEC Web of Conferences vol:82, issue:20168203008, page:1-
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