Search Results - "Irwanto, Dwi"

Tritium Breeding Performance Analysis of HCLL Blanket Fusion Reactor Employing Vanadium Alloy (V-5Cr-5Ti) as First Wall Material by Maemunah, Indah Rosidah, Su’ud, Zaki, Waris, Abdul, Irwanto, Dwi

“…Neutronic analysis in the HCLL blanket module has been established, and the calculation was performed by the ITER team, including the first wall (FW). In this…”
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Antioxidant Activity Between Defatted and Different Solvent Temperature in Rice Bran var. IR-64 Extract by Widyastuti, Retno, Dwi Irwanto, Rahmat, Purwati Nurlaili, Enny, Hartati, Sri, Iqrar, Irum

“…The extraction of bioactive components in rice bran is influenced by various factors, including defatted treatment and temperature. The aim of this study was…”
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Wall Effect Analysis in Thermal-Hydraulics Aspect of HTR-10 and PR-3000 Reactors Using Different Porosity Models by Bari, Bilal El, Irwanto, Dwi

“…Gen-IV is the latest generation of a nuclear reactor with better aspects than the previous generation, Pebble-Bed Reactor (PBR) is one of them. PBR using…”
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Moving particle semi-implicit simulation on the molten Wood’s metal downward relocation process by Hidayati, Anni Nuril, Waris, Abdul, Mustari, Asril Pramutadi Andi, Irwanto, Dwi, Aprianti, Nur Asiah

“…In the case of a severe accident involving nuclear reactors, an important aspect that should be considered is the leakage of molten material from the inside of…”
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Enhancing the performance of a long-life modified CANDLE fast reactor by using an enriched 208Pb as coolant by Widiawati, Nina, Su’ud, Zaki, Irwanto, Dwi, Permana, Sidik, Takaki, Naoyuki, Sekimoto, Hiroshi

“…The investigation of the utilization of enriched 208Pb as a coolant to enhance the performance of a long-life fast reactor with a Modified CANDLE (Constant…”
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Decay heat removal without forced cooling on a small simplified PBR with an accumulative fuel loading scheme by Irwanto, Dwi, Obara, Toru

“…•The passive safety feature was analyzed for a small simplified pebble bed reactor.•The decay heat is transferred through conduction and radiation.•The last…”
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A benchmark study of large-angle neutron scattering cross section of tungsten using two shadow bars technique at 14 MeV by Rosidah Maemunah, Indah, Araki, Sota, Miyazawa, Rio, Fukui, Kazuki, Tamaki, Shingo, Kusaka, Sachie, Irwanto, Dwi, Waris, Abdul, Su’ud, Zaki, Sato, Fuminobu, Murata, Isao

“…In fusion reactor design, neutron leaks intensively from blanket material through a gap. In this streaming phenomenon, backscattering cross section is known to…”
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Burnup characteristics and fuel cycle economics of mixed uranium-thorium fuel in a simplified small pebble bed reactor by Irwanto, Dwi, Obara, Toru

“…The limitation of natural uranium resources and the improvement of economic values of nuclear reactors are important issues to be solved in the future…”
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Burnup Characteristics of a Peu à Peu Fuel Loading Scheme in a 110MWt Simplified Pebble Bed Reactor by IRWANTO, Dwi, OBARA, Toru

“…The efficient use of nuclear fuel is one of the important issues in the current development of nuclear reactors due to the limitation of natural uranium…”
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Enhancing the performance of a long-life modified CANDLE fast reactor by using an enriched 208 Pb as coolant by Widiawati, Nina, Su'ud, Zaki, Irwanto, Dwi, Permana, Sidik, Takaki, Naoyuki, Sekimoto, Hiroshi

“…The investigation of the utilization of enriched 208Pb as a coolant to enhance the performance of a long-life fast reactor with a Modified CANDLE (Constant…”
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Properties of Oil Palm Empty Fruit Bunch-Filled Recycled Acrylonitrile Butadiene Styrene Composites: Effect of Shapes and Filler Loadings with Random Orientation by Nikmatin, Siti, Syafiuddin, Achmad, Irwanto, Dwi Arso Yedi

“…Exploration of natural resources as composite fillers is still under intensive investigation. Previous works mention that nano-size natural fillers provide an…”
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Design Study of 200MWth Gas Cooled Fast Reactor with Nitride (UN-PuN) Fuel Long Life without Refueling by Syarifah, Ratna Dewi, Yulianto, Yacobus, Su’ud, Zaki, Basar, Khairul, Irwanto, Dwi

“…Design study of 200 MWth Gas Cooled Fast Reactor with UN-PuN fuel long life without refueling has been done. GFR is one type reactor in Generation IV reactor…”
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Fissile utilization of uranium, thorium, and plutonium fuels for a 60 MWt block‐type high‐temperature gas‐cooled reactor by Irwanto, Dwi, Pratama, Ayu Lia

“…Summary High‐temperature gas reactor (HTGR) is one of the Generation IV nuclear reactors currently undergoing rapid development in the world. The utilization…”
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Computational analysis for predicting fission product release of PeLUIt-40 under normal operating conditions by Purwaningsih, Anik, Irwanto, Dwi, Purba, Julwan H.

“…PeLUIt (Pembangkit Listrik dan Uap untuk Industri) is an High Temperature Gas Cooled Reactor (HTGR)-based cogeneration reactor designed by the Indonesian…”
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3-Dimensional full core neutronic analysis for uranium nitride fuel CANDLE reactor using Monte Carlo MCNP6 code by Afifah, Maryam, Su’ud, Zaki, Trianti, Nuri, Irwanto, Dwi

“…•This work has demonstrated 3-dimensional geometrical modeling based on continuous energy for uranium nitride fuel with lead–bismuth cooled CANDLE reactor…”
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Comparative analysis on small modular reactor (SMR) with uranium and thorium fuel cycle by Amatullah, Amila, Permana, Sidik, Irwanto, Dwi, Aimon, Akfiny Hasdi

“…•Thorium Fuel Cycle has emerged as an appealing alternative fuel option to enhance SMR performance and safety.•Utilization of thorium fuel cycle requires…”
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Comparison of neutronic aspects in high‐temperature gas‐cooled reactor using ZrC and SiC Triso particle with 50 and 100 MWt power by Miftasani, Fitria, Su'ud, Zaki, Irwanto, Dwi, Permana, Sidik

“…Summary The use of zirconium carbide (ZrC) as a substitute for silicon carbide (SiC) has been proposed to improve the performance of coated particles for…”
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Core design selection for a long‐life modular gas‐cooled fast reactor using OpenMC code by Raflis, Helen, Su'ud, Zaki, Waris, Abdul, Irwanto, Dwi

“…Summary This paper discusses design selection with variation of the height‐to‐diameter (H/D) ratios and core‐blanket configuration for a long‐life modular…”
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Reflector materials selection for core design of modular gas‐cooled fast reactor using OpenMC code by Raflis, Helen, Muhammad, Ilham, Su'ud, Zaki, Waris, Abdul, Irwanto, Dwi

“…Summary This paper discusses the selection of reflector materials for the core design of modular gas‐cooled fast reactor (GFR). Ideally, the reflector…”
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Initial core design analysis of lead (208) ‐bismuth eutectic‐cooled reactor with radial fuel shuffling by Widiawati, Nina, Su'ud, Zaki, Irwanto, Dwi, Permana, Sidik, Takaki, Naoyuki, Sekimoto, Hiroshi

“…Summary Natural uranium is utilized in a small percentage by the Light Water Reactor (LWR) and also by the once‐through Fast Breeder Reactor. One of the…”
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