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121	Nanomaterial and Nanotechnology	ABS-46
Composite of graphene and in-situ polymerized polyaniline on carbon cloth substrate for flexible supercapacitor Albert Willy Jonathan Sembiring (a) and Afriyanti Sumboja (a*) a) Material Science and Engineering Research Group, Faculty of Mechanical and Aerospace Engineering, Institut Teknologi Bandung, Jl. Ganesha 10, Bandung, 40132 Indonesia. Email: afriyanti.sumboja[at]material.itb.ac.id Abstract Flexible and lightweight energy storage is required for powering wearable electronic devices. Among the developed energy storage devices, supercapacitors have gained much interest as energy storage for wearable applications through their long cycle life and high power density. This work presents a flexible supercapacitor based on carbon cloth coated with graphene/polyaniline nanocomposite. Graphene/polyaniline nanocomposite is adopted as active material due to its high stability and the synergistic feature of pseudocapacitive and electrical double layer capacitance. The nanocomposite is synthesized from aniline and graphene in the sulfuric acid solution containing carbon cloth by chemical oxidative method, allowing the aniline to polymerize directly on the carbon cloth and graphene. Flexible supercapacitor devices with PVA/H_{2}SO_{4} gel electrolyte exhibit an areal capacitance of 194.90 mF/cm2 at a scan rate of 5 mV/s. The device retains 77.21% of its initial capacitance after 500 cycles of cyclic voltammetry tests and exhibits a good performance when bent at 90&#7484- and 180&#7484-. This work demonstrates the exciting potentials of carbon cloth-based supercapacitors for high-performance wearable supercapacitors. Keywords: all-solid-state supercapacitor, graphene, polyaniline, flexible substrate Share Link | Plain Format | Corresponding Author (Albert Willy Jonathan Sembiring)

122	Nanomaterial and Nanotechnology	ABS-47
DFT Study on Gas Phase Decomposition of Ethylene Carbonate in the Presence of LiPF6, LiBF4, PF6-, and BF4- Farrel Dzaudan Naufal, Elbert Timothy Lasiman, Az Zahrah Fitriana Syafira, Muhammad Fadhlan Anshor, Dicky Setianto, Achmad Ubaidillah, Bernardus Rendy, Ganes Shukri, Adhitya Gandaryus Saputro Teknik Fisika ITB Abstract Battery degradation by electrolyte decomposition has been a well-known problem that attracts much attention, especially on its mechanism. The most common electrolyte on lithium-ion batteries is ethylene carbonate (EC) which acts as a solvent for lithium salts. In this work, we investigate the decomposition mechanism of EC in the presence of LiPF6, LiBF4, and their delithiated counterpart by means of first-principles density functional theory (DFT) calculations. We found that the energy barrier on BF4- anion presence is lower than PF6- anion presence about 0.42 eV (with Li+) and 0.22 eV (without Li+), suggesting that BF4- anion presence reduces EC stability more than PF6- anion. In both salt anion cases, the presence of Li+ ion increases the activation energy (0.79 eV on PF6-, 0.59 eV on BF4-) but decreases enthalpy change significantly (1.58 eV on PF6-, 1.43 eV on BF4-). While Li+ ion causes forward reaction rate to be slower, the relative forward-reverse rate increases drastically. This suggests that Li+ presence destabilizes the EC thus making it easier to decompose. Keywords: lithium-ion battery- electrolyte decomposition- ethylene carbonate- Li-salt -density functional theory Share Link | Plain Format | Corresponding Author (Adhitya Gandaryus Saputro)

123	Nanomaterial and Nanotechnology	ABS-48
DFT Study of Lithium Diffusion in La2O3 Elbert Timothy Lasiman, Farrel Dzaudan Naufal, Muhammad Fadhlan Anshor, Az Zahrah Fitriana Syafira, Dicky Setianto, Achmad Ubaidillah, Bernardus Rendy, Ravanny Waraney Moesa Komalig, Ganes Shukri, Adhitya Gandaryus Saputro Teknik Fisika ITB Abstract Surface coating may suppress side reactions between electrode and electrolyte in Lithium-Ion Batteries (LIBs), but may also affect the rate and power capability of the batteries. Lanthanum Oxide (La2O3) coating has been experimentally shown to enhanced LIBs performance. In this study, we investigate the diffusion of Li in bulk La2O3 to understand the enhanced electrochemical performance of several La2O3-coated Li-ion battery cathodes. We use Density Functional Theory (DFT) with Climbing Image Nudged Elastic Band (CI-NEB) to calculate the energy barrier and the diffusivity. Among the three considered pathways, our results suggest that one pathway has a low Li energy barrier of 0.09 eV. This finding suggests that Li will preferably diffuse along the [100] and [010] directions. Furthermore, we find that Li will diffuse more slowly along the [001] direction. Keywords: lithium-ion battery- cathode coating- Li diffusion- La2O3 - density functional theory Share Link | Plain Format | Corresponding Author (Adhitya Gandaryus Saputro)

124	Nanomaterial and Nanotechnology	ABS-72
Composite of graphene and in-situ polymerized polyaniline on carbon cloth substrate for flexible supercapacitor Albert Willy Jonathan Sembiring (a) and Afriyanti Sumboja (a*) a) Material Science and Engineering Research Group, Faculty of Mechanical and Aerospace Engineering, Institut Teknologi Bandung, Jl. Ganesha 10, Bandung, 40132 Indonesia. Email: afriyanti.sumboja[at]material.itb.ac.id Abstract Flexible and lightweight energy storage is required for powering wearable electronic devices. Among the developed energy storage devices, supercapacitors have gained much interest as energy storage for wearable applications through their long cycle life and high power density. This work presents a flexible supercapacitor based on carbon cloth coated with graphene/polyaniline nanocomposite. Graphene/polyaniline nanocomposite is adopted as active material due to its high stability and the synergistic feature of pseudocapacitive and electrical double layer capacitance. The nanocomposite is synthesized from aniline and graphene in the sulfuric acid solution containing carbon cloth by chemical oxidative method, allowing the aniline to polymerize directly on the carbon cloth and graphene. Flexible supercapacitor devices with PVA/H_{2}SO_{4} gel electrolyte exhibit an areal capacitance of 194.90 mF/cm2 at a scan rate of 5 mV/s. The device retains 77.21% of its initial capacitance after 500 cycles of cyclic voltammetry tests and exhibits a good performance when bent at 90&#7484- and 180&#7484-. This work demonstrates the exciting potentials of carbon cloth-based supercapacitors for high-performance wearable supercapacitors. Keywords: all-solid-state supercapacitor, graphene, polyaniline, flexible substrate Share Link | Plain Format | Corresponding Author (Afriyanti Sumboja)

125	Nanomaterial and Nanotechnology	ABS-76
Spin current generation by edge plasmon M Shoufie Ukhtary(a*) , Yuan Tian (b), Riichiro Saito (b) a) Research Center for Physics, Indonesian Institute of Sciences * msho001[at]lipi.go.id b) Department of Physics, Tohoku University Abstract Spin current is defined as the difference between charge currents of the spin up and down. The conventional method to generate spin current requires a magnetic material. In this work, we discuss the generation of spin current without magnetic material. Here, the spin current is generated by edge plasmon (EP) on a graphene ribbon. EP is an electromagnetic wave that propagates along the edges of the ribbon and the electric field is localized near the edges. In contrast with the surface plasmon on 3D metal, the electric field of EP rotates on the plane of graphene that corresponds to the transverse and out-of-plane optical spin. We found that the spin current flows on the surface of graphene with spin-polarization in the out-of-plane direction. Further, the spin current induced by EP is tunable not only by the frequency, but also by the Fermi energy of graphene, which enables application for a spin-switching device controlled by light and gate voltage Keywords: Spintronics, Graphene, Surface Plasmons Share Link | Plain Format | Corresponding Author (M Shoufie Ukhtary)

126	Nanomaterial and Nanotechnology	ABS-133
Preparation of Platina Nanoparticles with the Presence of Cellulose Nano Crystals Arie Wibowo1,2, Rachmad Santoso1, Hermawan Judawisastra1 and Yogi Wibisono Budhi2,3,a 1 Materials Science and Engineering Research Group, Faculty of Mechanical and Aerospace Engineering, Institut Teknologi Bandung, Jl. Ganesha 10, 40132, Bandung, Indonesia 2 Research Center for Nanoscience and Nanotechnology, Institut Teknologi Bandung, Jl. Ganesha 10, 40132, Bandung, Indonesia 3 Department of Chemical Engineering, Institut Teknologi Bandung, Jl. Ganesha 10, 40132, Bandung, Indonesia Abstract Platina play a crucial role in catalytic converter device as one of catalyst that convert toxic gases in the exhaust gas emission to less toxic gas pollutant. The performance of this device can be significantly elevated by implementing platina nanoparticles (Pt NPs) because catalytic performance can be increased by decreasing its particles size. However, nanoparticles are not stable and tend to agglomerate, thus prohibit formation of nano particles. In this context, utilization of cellulose nano crystals (CNCs) in fabrication of Pt NPs are attractive due to their ability to encourage nucleation and prevent agglomeration of nanoparticles. In this study, Pt NPs was prepared by reduction of H2PtCl6 solution at various temperature (25, 33 and 40 C) with the presence of CNCs. Based on visual observation, darker precipitate was observed by increasing temperature. Further characterization using UV-Vis spectroscopy showed that about 90% of Pt4+ in solution were successfully convert to dark particles at 40 C. Transmission electron microscopy (TEM) and selected area electron diffraction (SAED) revealed that the dark particles in sample is Pt NPs with particles size 16.5 nm. Keywords: catalytic converter, cellulose nano crystals, nano catalyst, platina nanoparticles, reduction Share Link | Plain Format | Corresponding Author (arie wibowo)

127	Nanomaterial and Nanotechnology	ABS-177
DEVELOPMENT OF COVID DETECTION USING SPR SENSORS: A PRELIMINARY RESULTS Feraliana,1 Sarah Zulfa Khoirunnisa,1 Ni Luh Wulan Septiani,2 Muhammad Iqbal,2 Tati Sutarti, 4 Husna Nugrahapraja,3 Brian Yuliarto1,2 1Research Center for Nanosciences and Nanotechnology, Institut Teknologi Bandung, Bandung 40132, Indonesia 2Advanced Functional Materials Research Group, Institut Teknologi Bandung, Bandung 40132, Indonesia 3Genetics and Molecular Research Group, Institut Teknologi Bandung, Bandung 40132, Indonesia 4Bandung City Health Department, Bandung 40122, Indonesia Abstract Coronavirus or Covid-19 is a virus from the Coronaviridae family that has been epidemic throughout the world since the end of 2019. The virus spreads ten times faster through human interaction than SARS-CoV. RNA sequence of Covid-19 has 79,5% similarity with SARS-CoV. Fast and specific detection of Covid-19 is needed so that patient detection can be done quickly and accurately. One method that can be developed as a Covid-19 biosensor is aptamers-based biosensors. Aptamers are artificial oligonucleic acids that can specifically bind to target molecules. Aptamers are easily chemically modifiable for increasing stability and reducing toxicity. They show a comparable affinity for the target virus and better thermal stability than monoclonal antibodies. Those advantages make aptamers promising candidates in diagnostic and detection applications. The goal of this research was to use RNA aptamer as the specific recognition element in a portable surface plasmon resonance (SPR) biosensor for the detection of Covid-19 in humans. Aptamer RNA 1 Covid-19 was designed using the Covid-19 sequence from Gisaid using the in silico method. End of 3^ aptamer RNA 1 modified with dithiol. Then, the aptamer was immobilized on the gold nanoparticle sensor surface via Cysteine-dithiol binding. The RNA solution that had been extracted from swab samples, was diluted ten times before being used as a sample. The immobilized aptamer RNA 1 captured Covid-19 in RNA solution, causing an increase in refraction index (r.u). Aptamer RNA 1 was found to bind RNA virus of Covid-19 where the positive sample of Covid-19 has refraction index (r.u) between 3 r.u - 10 r.u for various Ct values. Keywords: aptamer- RNA- small molecule- aptasensor- oligonucleotide- biosensor- Share Link | Plain Format | Corresponding Author (Feraliana Feraliana)

128	Nanomaterial and Nanotechnology	ABS-178
Modification of screen-printed carbon electrode (SPCE) by the Nafion functionalized silicon nanoparticles (SiNPs/Naf) materials in non-enzymatic electrochemical sensor for uric acid (UA) detection Nurul Huda (1), Poetro Lebdo Sambegoro (2), Ni Luh Wulan Septiani (1), Muhammad Iqbal (1), Amalia Sholehah (3),(4), Brian Yuliarto (1*),(5) 1) Advanced Functional Material Research Group, Faculty of Industrial Technology, Institut Teknologi Bandung, Jl. Ganesha No. 10, Bandung, Jawa Barat, 41032, Indonesia 2) Faculty of Mechanical and Aerospace Engineering, Institut Teknologi Bandung, Bandung, Indonesia 3) Advanced Materials and Tomography Laboratory, Faculty of Engineering, Universitas Sultan Ageng Tirtayasa, Jl. Jenderal Sudirman Km. 3 Cilegon, Banten, 42435, Indonesia 4) Departement of Metallurgical Engineering, Faculty of Engineering, Universitas Sultan Ageng Tirtayasa, Jl. Jenderal Sudirman Km. 3 Cilegon, Banten, 42435, Indonesia 5) Research Center for Nanosciences and Nanotechnology (RCNN), Institut Teknologi Bandung, Jl. Ganesha No. 10, Bandung, Jawa Barat, 41032, Indonesia *brian[at]tf.itb.ac.id Abstract A non-enzymatic electrochemical sensor has been successfully developed to detect uric acid (UA) based on a modified screen-printed carbon electrode (SPCE) using Nafion functionalized silicon nanoparticles. Silicon nanoparticles (SiNPs) material is used because of their advantages, including its abundant availability, good biocompatibility, and adjustable porosity and surface area according to the synthesis method used. Nafion is a sulfonated tetrafluoroethylene-based fluoropolymer-copolymer that has been widely used for electrochemical sensors and is functioned as a stabilizer of the sensor. In this study, SiNPs material was successfully synthesized through the non-thermal chemical vapor deposition method. XRD diffractogram and SEM image confirmed its structure and morphology. The crystallinity of the produced SiNPs is 69.85%. SEM-EDS characterization was also carried out to confirm the success of the SPCE modification by SiNPs and SiNPs/Naf materials. The changes in the morphology of SPCE and the EDS spectrum that were measured indicated the success of the SPCE modification process for each stage. Cyclic voltammetry, electrochemical impedance spectroscopy, and differential pulse voltammetry study were used to analyze the electrochemical characteristics and performance of non-enzymatic electrochemical sensors based on SPCE/SiNPs/Naf structures against uric acid analytes. Based on the results of electrochemical analysis, the sensitivity, detection limit, and quantification limit of the sensor are 0.01 uA.mM-1.cm-2, 0.21 uM, and 0.69 uM respectively in the linear measurement range of uric acid concentration of 10 - 1000 uM. Then, a sensor stability study was also carried out which resulted in an RSD value of 4.83%. Keywords: non-enzymatic electrochemical sensors, SPCE, SiNPs, Nafion, uric acid Share Link | Plain Format | Corresponding Author (Nurul Huda)

129	Nanomaterial and Nanotechnology	ABS-179
PREPARATION OF BIMETALLIC METAL-ORGANIC FRAMEWORK DERIVED FROM SPHERICAL Ni-Co GLYCERATE TEMPLATE Muhammad Zimamul Adli,1,2 Ni Luh Wulan Septiani,2 Muhammad Iqbal, 2 Irzaman,3 Widagdo Sri Nugroho,4 Febdian Rusydi,5 Brian Yuliarto1,2 1Research Center for Nanosciences and Nanotechnology, Institut Teknologi Bandung, Bandung 40132, Indonesia 2Advanced Functional Materials Research Group, Institut Teknologi Bandung, Bandung 40132, Indonesia 3Physics Department, Faculty of Mathematics and Natural Sciences, IPB University, Bogor 16680, Indonesia 4Departement of Veterinary Public Health, Faculty of Veterinary Medicine, Universitas Gadjah Mada, Yogyakarta 55281, Indonesia 5Department of Physics, Faculty of Science and Technology, Universitas Airlangga, Surabaya 60115, Indonesia Abstract Bimetallic Metal-Organic Framework (MOF) have attracted significant interest due to its high specific surface area and tunable porosity, leading to high sensitivity and catalytic activity. This work studies on the characteristics of Ni/Co-MOF synthesized through self-template using uniform Ni-Co glycerate spheres. Nickel and cobalt are active electrode materials with a similar properties and atomic radius, and have many possible coordination with ligands so that they can be found in many types of MOFs. In this work Ni-Co Glycerate, that was produced in powder form, was used as a source of metal ions, 2-methylimidazole (H-MeIM) as a ligand as well as aquabidest and ethanol as solvents. The MOF was produced using two step processes first is solvothermal for glycerate formation and second, is MOF formation at room temperature. The XRD results showed that the Ni/Co-MOF is in an amorphous phase because there is no peak was observed. The results of the Scanning Electron Microscope (SEM) analysis showed that the Ni/Co-MOF has spherical shape covered by nanosheets that are suspected to be amorphous MOF. In this preliminary study, we would like to explore the preparation, properties, and applications of amorphous MOF. Because amorphous MOF presents many opportunities as new functional materials especially in electrochemical applications. Keywords: metal-organic frameworks, bimetallic, nickle, cobalt, amorphous Share Link | Plain Format | Corresponding Author (Muhammad Zimamul Adli)

130	Nanomaterial and Nanotechnology	ABS-180
Photoluminescence Properties of CsPbCl3 and CsPbBr3 Nanocrystals synthesized by LARP Method with Various Ligands and Anti-solvents Valdi Rizki Yandri1,2, Priastuti Wulandari1, and Rachmat Hidayat*1 1 Physics of Magnetism and Photonics Research Division, Faculty of Mathematics and Natural Sciences, Institut Teknologi Bandung, Jl. Ganesha 10 Bandung 40132. Indonesia 2 Power Electronics Laboratory, Polytechnic State of Padang, Limau Manis Padang 25164. Indonesia * Abstract Cesium lead halide (CsPbX3- X=Cl, Br, I) are all-inorganic perovskite materials that can be synthesized by some methods such as hot injection, solvent-induced reprecipitation, microwave assisted, ligand assisted reprecipitation (LARP) and mechanochemical method. In this research, we report synthesis of CsPbCl3 and CsPbBr3 nanocrystals (NC) that was synthesized from CsCl and PbCl2 by the LARP method at room temperature in dimethyl sulfoxide (DMSO) solvent. CsPbBr3 NC was also synthesized by a similar method from CsBr and PbBr2. CsPbCl3 and CsPbBr3 were synthesized by using different ligand (i.e. linoleic acid (LA) and oleic acid (OA)). Besides that, antisolvent was varied to two anti-solvents, i.e. chloroform, toluene, and tetrahydrofuran (THF). The XRD patterns of those nanoparticles indicates that their crystal structures are cubic with space group Pm-3m (221). Lattice constants are 5.61 A for CsPbCl3 and 5.83 A for CsPbBr3. The PL peak of CsPbCl3 NC emerges at around 435 - 437 nm, whereas for CsPbBr3 NC at around 516 - 526 nm. Keywords: CsPbCl3, CsPbBr3, nanocrystals, perovskite materials, LARP method Share Link | Plain Format | Corresponding Author (Valdi Rizki Yandri)

131	Nuclear Science and Engineering	ABS-10
The effect of Copper utilization on MSFR^s safety plug performance simulation by using MPS Nita Juli Yanti (a*), Anni Nuril Hidayati (b), Asril Pramutadi Andi Mustari (b), Nur Asiah Aprianti (b) a) Bachelor Program of Physics Departement, Faculty of Mathematics and Natural Science, Bandung Institute of Technology Jalan Ganesha 10, Bandung 40132, Indonesia *nitajuliyanti091[at]gmail.com b) Nuclear Physics And Biophysics Research Division, Physics Departement, Faculty of Mathematics and Natural Science, Bandung Institute of Technology Jalan Ganesha 10, Bandung 40132, Indonesia Abstract Generation IV reactors are developed and expected to have a higher safety level than the previous reactors. One of the generation IV reactors is Molten Salt Fast Reactor (MSFR) with the freeze plug and drainage pipe as the integrated safety system. When an accident occurs, the fuel flows down, directly interact and melt the freeze plug. Moreover, the fuel will be cooled at the safety tank. This research aims to simulate the freeze plug melting process by using Moving Particle Semi Implicit (MPS) method. MPS is a particle method based on Lagrangian mechanism developed by Koshizuka and Oka in 1996. Mainly, the freeze plug consisted of frozen salt and Hastelloy N. There were two kind of freeze plug geometries used in the simulation, which are with and without copper. The Copper^s thickness was varied between 1.5 - 3.0 mm with 0.5 mm interval. The additional Copper^s thickness was performed toward the inside of the freeze plug. The height and the radius of freeze plug were 30 mm. The thickness of Hastelloy N and the copper were 8.5 mm and 2.5 mm, respectively. A s-curve temperature distribution was initially applied due to the transfer heat between molten salt and the freeze plug material. The results show the melting time of with and without copper cases were 125 s and 250 s, respectively. Moreover, the thicker copper led to the faster freeze plug melting process. Therefore, the most optimal thickness of the copper was 3.5 mm. Keywords: Freeze Plug, Heat Transfer, Melting Process, Moving Particle Semi Implicit, Particle Share Link | Plain Format | Corresponding Author (Nita Juli Yanti)

132	Nuclear Science and Engineering	ABS-23
Neutronic Analysis of TMSR-500 Reactor Core Alessandro Widjati, Sidik Permana, Syeilendra Pramuditya Institut Teknologi Bandung Abstract TMSR500 has potential to provide energy that are sustainable, safe, and low in CO2 emissions in Indonesia. Therefore study about TMSR500 will have a significant impact on the development of nuclear energy in Indonesia. Neutronic analysis of TMSR500 core will be conducted in this study. Influence of fuel composition, fuel volume fraction, coolant quantity, and material temperature on reactor criticality will be evaluated. The method used to obtain the neutronic aspects of the reactor is neutronic calculation by computer simulation using the SRAC2006 code system and the JENDL4.0 nuclear library. The data obtained for neutronic analysis are graph of keff against time for each design parameter variation, graph of reactivity against relative coolant nuclide density and relative temperature, and coolant nuclide density and temperature reactivity coefficient at BOL. The data shows that the fissile material is directly proportional to keff. While fuel volume fraction is inversely proportional to keff at BOL. Coolant nuclide density and fuel salt-graphite temperature are inversely proportional to keff and reactivity. With fuel volume fraction value of 27 percent, TMSR-500 core requires minimum U-235 concentration of 1.14 percent to achieve criticality. TMSR-500 core have a negative coolant nuclide density and temperature reactivity coefficient at BOL, where the value are -0.02764 (cm cubic) and -0.00003864 (/K) respectively. Keywords: coolant, fuel composition, fuel volume fraction, material temperature, neutronic, TMSR. Share Link | Plain Format | Corresponding Author (Alessandro Widjati)

133	Nuclear Science and Engineering	ABS-38
Computational fluid dynamics analysis of the natural circulation system in vertical heater horizontal cooler (VHHC) molten salt loop Duwi Hariyanto(1)(4), Sidik Permana(1)(2), Abdul Waris(1)(2) and Suprijadi(3) (1)Nuclear Physics and Biophysics Research Division, Physics Department, Institut Teknologi Bandung (2)Nuclear Science and Engineering Department, Institut Teknologi Bandung (3)Theoretical High Energy Physics and Instrumentation Research Division, Physics Department, Institut Teknologi Bandung (4)Instrumentation and Automation Engineering Study Program, Production and Industrial Technology Department, Institut Teknologi Sumatera Abstract Molten salt has attracted the attention of researchers, especially as a coolant because of its characteristics. The purpose of this study is to analyse the transient and steady state of the natural circulation system in the molten salt loop with vertical heater and horizontal cooler using computational fluid dynamics. The computational fluid dynamics module in the COMSOL Multiphysics software is used to solve governing equations. Experimental data from several references are used as input data in modelling. The loop is modelled as a rectangular loop with Inconel 625 as the pipe material and molten salt (NaNO3+KNO3) as the working fluid. The variation of heater power is also carried out in modelling. The modelling results show good agreement with the experimental results. The results provided that the molten salt natural circulation loop with vertical heater and horizontal cooler showed good flow stability without reversal of flow direction. Keywords: molten salt, computational fluid dynamics, natural circulation, instability Share Link | Plain Format | Corresponding Author (Duwi Hariyanto)

134	Nuclear Science and Engineering	ABS-89
Simulation of the Stratification Process of Some Liquid Salts by Using the Moving Particle Semi Implicit Method Y. Yulianto (1), A. P. A. Mustari (2*) and A. Baliana (3) 1) Advanced Nuclear Laboratory, Physics Department, Institut Teknologi Bandung (Jl. Ganesha 10, Bandung 40132, Indonesia) 2) Nuclear Physics and Biophysics Research Division, Physics Department, Institut Teknologi Bandung (Jl. Ganesha 10, Bandung 40132, Indonesia) *Corresponding author: pramutadi[at]fi.itb.ac.id 3) Law Faculty, Tadulako University (Jl. Soekarno Hatta No. KM. 9, Tondo, Mantikulore, Palu, Sulawesi Tengah 94148) Abstract The use of liquid fuel is one of the developments blooming in nuclear technology. Molten Salt Reactor leads the new technology in nuclear engineering in using liquid fuel. One of the interesting phenomena about using liquid fuel is how the inter-liquid fuel interacts, especially its stratification behavior. In this study, some components of the liquid salts (i.e. NaCl, KCl, KBr, and NaBr) interacted with Fe were investigated to understand the stratification behavior of these liquid salts by simulation in the framework of the Moving Particle Semi-Implicit (MPS). The obtained results show the typical results of stratification with different physical properties. On the other hand, these results are good enough in explaining the interaction inter-liquid. The density of the salt liquid has a significant effect on the stratification process. Besides, the kinematics viscosity of the liquid salt also affects the liquid salt in gaining the stratification condition. These results are very important information to conduct the next study about liquid salts. Keywords: Inter-liquid- Liquid salt- Molten salt- MPS- Stratification Share Link | Plain Format | Corresponding Author (Yacobus Yulianto)

135	Nuclear Science and Engineering	ABS-109
Numerical Investigation of Freeze Valve Melting Behavior in Molten Salt Reactor using OpenFOAM Robi Dany Riupassa (a), Khairul Basar (b), Novitrian (b), and Abdul Waris (b*) (a) Department of Physics, Faculty of Mathematics and Natural Sciences, Institut Teknologi Bandung, Jalan Ganesha 10, Bandung 40132, Indonesia (b) Nuclear Physics and Biophysics Research Division, Department of Physics, Faculty of Mathematics and Natural Sciences, Institut Teknologi Bandung, Jalan Ganesha 10, Bandung 40132, Indonesia *awaris[at]fi.itb.ac.id Abstract Molten Salt Reactor (MSR) used a freeze valve to handle accident conditions when the reactor overheated and the active safety control systems failed. The freeze valve will melt if the reactor core temperature increases and exceeds the freeze valve^s melting temperature. In this research, a numerical investigation of freeze valve melting behavior was conducted. Freeze valve geometry used geometry proposed by Oak Ridge National Laboratory (ORNL) in Molten Salt Reactor Experiment (MSRE) and also used in test loop facility in Shanghai Institute of Applied Physics (SINAP) to develop Thorium Molten Salt Reactor (TMSR). The material used FLiNaK salt (LiF-NaF-KF, 46.5-11.5-42.0 mol %). Numerical calculation performs using OpenFOAM. BuoyantPimpleFoam was used to analyze the heat transfer mechanism. Isothermal phase-change simulated by adding solidificationMeltingSource terms into fvOptions as a flexible framework in OpenFOAM. Keywords: Freeze valve- MSR- OpenFOAM Share Link | Plain Format | Corresponding Author (Robi Dany Riupassa)

136	Nuclear Science and Engineering	ABS-119
Design Study of Very Small Modular Gas Cooled Fast Reactors Zaki Su^ud(1), Feriska H. Irka(1), Fitria Miftasani(1), Nina Widiawati(1),Hellen Raflis(1), Indah Rosyidah M.(1), Nur Asiah Aprianti (1), Zuhair(2) 1 Dept of Physics, Bandung Institute of Technology (ITB) 2 Center for Reactor Technology and Safety (PTRKN) BATAN Abstract Very small modular reactors have become important topic in advanced next generation Nuclear Power Plant development. In this study very small modular nuclear power plants (NPPs) with 1-20 MWe power level have been developed conceptually using SRAC, FI-ITB CH1, and MCNP codes. order to obtain compact core, relatively high plutonium content are used in the nuclear reactor core designs. up to 20% of heavy metals. In addition, Np-237 have been used to reduce excess reactivity during 10 - 30 years operation times without refueling or fuel shuffling. The reactor cores are designed to have relatively small radius in order to anticipate core depressurized accident. In case of core depressurized accident the increased temperature will inherently shut down the reactor and the decay heat will be removed through natural circulation of air through outer part of the core and at the central hole. The excess reactivity has been minimized to be less that 3% dk/k. The core are divided into three core regions with different plutonium content to reduce excess reactivity during burn-up and to extend operation time without refueling or fuel shuffling. Preliminary safety alanysis also presented in this study especially estimation of macimum temperature during core depressurized accident. Keywords: GCFR, very small reactor, modular, long life operation, core depressurized accident Share Link | Plain Format | Corresponding Author (Burhan Izzudin)

137	Nuclear Science and Engineering	ABS-130
Parametric Study of Thorium Fuel Utilization on Small Modular Pressurized Water Reactors (PWR) Boni Pahlanop Lapanporo(1,3*), Zaki Suud(1,2), Asril Pramutadi Andi Mustari(1,2) 1) Department of Physics, Faculty of Mathematics and Natural Sciences, Institut Teknologi Bandung, Jl. Ganesa 10 Bandung 40132, INDONESIA 2) Nuclear Physics & Biophysics Research Division, Department of Physics, Faculty of Mathematics and Natural Sciences, Institut Teknologi Bandung, Jl. Ganesa 10 Bandung 40132, INDONESIA 3) Department of Physics, Faculty of Mathematics and Natural Sciences, Universitas Tanjungpura, Jl. Prof. Dr. H. Hadari Nawawi Pontianak 78124, INDONESIA *boni8poro[at]physics.untan.ac.id Abstract Small Modular Pressurized Water Reactor (PWR) can be used to overcome the problem of electricity shortages in remote areas with fewer populations. These reactors usually use uranium-based fuel. Currently, the use of thorium-based fuels for this type of reactor has received constant attention, leading to several investigations of fuel performance. This study aims to determine the performance of thorium-based fuel in the PWR core at a power level of 300 MWt. The analysis was carried out by varying the percentage of U-233 as fissile material in Thorium (Th-233U)O2 fuel by 3%-8% and Pa variation as burnable poison 0.2%-5%. In addition, analysis of changes in the volume fraction of fuel ranging from 40%-60%, with the type of cladding used in the form of Zirlo. The calculation system uses the SRAC computer code with PIJ and CITATION modules, respectively, for cell calculations and core calculations, using JENDL-4.0 nuclide data. Parameters analyzed from the fuel cell calculation results are reactor criticality and excess reactivity. The analysis results show that the best fuel performance is found in cells with a fuel volume fraction of 60%, U-233 configuration on the fuel of 4-5-6%, and the addition of 2.5% Pa-231. This fuel configuration can achieve cycles of up to 19 years with excess reactivity at BOL of 2.57% dk/k and excess reactivity at EOL of 0.87% dk/k. Keywords: neutronic analysis- burnup analysis- reactivity, Share Link | Plain Format | Corresponding Author (Boni Pahlanop Lapanporo)

138	Nuclear Science and Engineering	ABS-137
Comparative Evaluation on Nuclear Shell Correction Calculation using Regulation Bayesian and Moving Average Methods Rizal Kurniadi Physics ITB Abstract Since Strutinsky had proposed a shell correction for nuclear mass calculations in 1967, there has been much further research on this topic. In addition to the development carried out on the Strutinsky method, some studies try to apply the shell correction. This paper is included in the development of the shell correction method. There are two techniques used in this work the first is the average method, while the second is the Bayesian regulation method. The two techniques are very different from those Strutinsky originally developed. He used the hermit polynomial as an extension of delta Dirac. This paper will show a comparative study of the two alternative techniques for calculating shell correction. Keywords: Nuclear Share Link | Plain Format | Corresponding Author (Rizal Kurniadi)

139	Nuclear Science and Engineering	ABS-139
Implementation of LSD Fission Barrier in Fission Cross Section Calculations Rizal Kurniadi Physics ITB Abstract In this paper, fission cross section of Th-232(n,f) and U-238(n,f) would be calculated using fission barrier parameter that obtained from Lublin-Strassbourg Drop Model (LSD) in statistical model framework. This model had been derived from modern liquid drop (NLD) by adding first order curvature term that depends on deformation parameter. This term is resulted from implementation of Leptodermous expansion of the nuclear energy. Deformation function that involved in LSD formulation is obtained from Funny Hills nuclear shape parameterization. All the obtained result then would be compared with another result that calculated using ETFSI (Extended Thomas Fermi and Strutinsky Integral ) method and experimental fission cross section that had been extracted from ENDF data. Keywords: Nuclear Share Link | Plain Format | Corresponding Author (Rizal Kurniadi)

140	Nuclear Science and Engineering	ABS-147
THE SIMULATION OF DEEP TRENCHES ETCHED SILICON PN JUNCTION BASED BETAVOLTAIC USING Ni-63 RADIOISOTOPE SOURCE Swastya Rahastama(1), Abdul Waris (2), Ferry Iskandar (2), Sparisoma Viridi (2) (1) Institut Teknologi Kalimantan (2) Institut Teknologi Bandung Abstract In basic planar betavoltaic structure, some of beta particles are not utilized effectively to generate electron-hole pairs inside the semicondutor. In order to improve the utilization of beta source that would be deposited at the surface of the battery, we proposed the deep trenches design and calculated the prediction model of its electrical performance using finite difference minority carrier diffusion equation (FD-MCDE). The deep trenches p-n junction was evaluated by dividing it into several regions according to the energy deposition profile at each cell. Herein, we employ Ni-63 radioisotope as the beta source coupled with silicon semiconductor. In comparison to the basic planar design, the deep trenches could give an overall improvement in electrical performance, which the maximum power density and conversion efficiency can be increased about 29.60%. Keywords: betavoltaic, deep trenches, silicon, Ni-63 Share Link | Plain Format | Corresponding Author (Swastya Rahastama)

141	Nuclear Science and Engineering	ABS-155
Neutronic Analysis of Core Shape and H/D Ratio in Small Molten Salt Fast Reactor 20-50 MWth with 235U as Fisile Material Dini Suci Lestari (a*), Cici Wulandari (a), Abdul Waris (b), dan Sidik Permana (b) a) Departemen Fisika, Fakultas Matematika dan Ilmu Pengetahuan Alam, ITB, Bandung b) Pusat Penelitian Fisika Nuklir dan Biofisika, Departemen Fisika, Fakultas Matematika dan Ilmu Pengetahuan Alam, ITB, Bandung Abstract The annual report from the United Nations (UN) which states that in 2019, carbon dioxide emissions related to the world^s energy supply increased to 33.3 Gt, or about 45% from 2000. New source of energy are needed for this reason for which exclude greenhouse gasses as it^s product. Nuclear is the obvious choice as long also contribute to the action to fulfill energy demand that highly increase. But nuclear industry has been sleeping for years because of unfertile market. Many investors would not invest due to large amount of fund and long amount of time are required to build full nuclear power plant which implied to high cost electric energy produced by nuclear. Small Modular Reactor (SMR) would be a great escape plan for nuclear. with Gen IV Molten Saltf Reactor type of SMR, which provide to the idea of producing smaller and more compact yet safe design. It^s also nourish the idea of having a high energy source in the comfort of small geometry. The sizes are varied based on the reactor output power, namely 50MW, 30MW, and 20MW. For 50 MWth output power reactor reach criticality at composition of LiF 85.5% + ThF4 10.5% + 235UF4 4% and reach critical radius of 44.13cm and a ratio of H/D=0.9. For 30 MWth output power reactor, the critical fuel composition is LiF 85.5% + ThF4 10.5% + 235UF4 5%, with a radius of 37.9 cm and a ratio of H/D=0.9. For 20 MWth output power reactor, the critical fuel composition is LiF 89 % + ThF4 8.1% + 235UF4 3.9%, with a radius of 36.9 cm and a ratio of H/D=0.9 Keywords: Geometry, MSFR, H/D, SMR, neutronic. Share Link | Plain Format | Corresponding Author (Dini Suci Lestari)

142	Nuclear Science and Engineering	ABS-164
Development of nuclear radiation detectors for environmental monitoring : a review Imam Ghazali Yasmint (a*), Sidik Permana (a) a) Department of Physics, Faculty of Mathematics and Natural Sciences, Bandung Institute of Technology, Ganesha No. 10 Bandung, Indonesia, 40132 *20220027[at]mahasiswa.itb.ac.id Abstract Radiation monitoring around the human environment has become one of Indonesia^s research priorities for the next few years. This monitoring is important because Indonesia has many medical and industrial facilities that utilize nuclear technology, so that, it is expected to prevent leakage of nuclear materials and other things that can have an impact on humans. In environmental monitoring, the selection of the right radiation detector is one of the important points. In this paper, we will review the development of nuclear radiation detectors, with an emphasis on applications for environmental monitoring. It will also explain the state of the art and the limitations of each detector so that developments that may be possible can be seen in the future. Keywords: Human Environment- Nuclear Detector- Radiation Monitoring Share Link | Plain Format | Corresponding Author (Imam Ghazali Yasmint)

143	Nuclear Science and Engineering	ABS-169
Microstructure Investigation of Mechanically Alloyed SS316L-6Al Oxide Dispersion Strengthened Steel Powder Abu Khalid Rivai (a*), Kandias Ahmad Muzaqi Nafsah Pratama (b), Bambang Sugeng (a) BATAN - Badan Tenaga Nuklir Nasional a) Center For Science and Technology of Advanced Materials - PSTBM, Kawasan Puspiptek Gd. 43, Tangerang Selatan, Banten, 15314 *rivai.abukhalid[at]batan.go.id UNTIRTA - Universitas Sultan Ageng Tirtayasa b) Teknik Metalurgi, Jl. Jenderal Sudirman Km 3, Kotabumi, Kec. Purwakarta, Kota Cilegon, Banten 42435 Abstract Development of accident-tolerant fuel (ATF) cladding materials for LWR (Light Water Reactors) is being intensively carried out in many research centers in the world as the lesson-learned from the Fukushima Daiichi nuclear reactor power plant accident. One of the advanced high temperature materials which is intensively developed is Oxide Dispersion strengthened (ODS) steel. The strengthened mechanism is generate by homogeneous dispersion of nano-meter sized ceramic oxide particles in the matrix of the steel which is done by mechanical alloying technique so called mechanosynthesis. Synthesis of an austenitic ODS steel powder of SS316L with additional element of 4% aluminum and dispersion of nano-particles of 0.5% yttrium oxide (yttria: Y2O3) has been done. The aim of the research is to achieve a better performance at elevated temperature of SS316L steel as an established material for power plants. Mechanosynthesis was done using High Energy ball Milling (HEM) for 30 hours with BPR (Ball to Powder Ratio) of 10:1. Afterward, the sample was characterized using Scanning Electron Microscope-Energy Dispersive Spectroscope (SEM-EDS) and X-ray diffraction (XRD) to analyze the microstructure characteristics. The results showed that the alloying between SS316L and aluminum powders was formed. Furthermore, crystal grains and the particles of SS316L-4Al-0.5Y2O3 powder was smaller than as received SS316L and aluminum powders. Keywords: High Temperature Materials, Steel, Microstructure, Mechanical Alloying, Oxide Dispersion Strengthened Share Link | Plain Format | Corresponding Author (Abu Khalid Rivai)

144	Nuclear Science and Engineering	ABS-170
Investigation On Oxidation Behavior of Nuclear Graphite IG-110 At Elevated Temperature Abu Khalid Rivai (a*), Herlina (b), and Sigit Tri Wicaksono (b) a) Center For Science and Technology of Advanced Materials, BATAN, Kawasan PUSPIPTEK Gedung 71, Tangerang Selatan, Banten 15314, Indonesia *rivai.abukhalid[at]batan.go.id b) Department of Materials and Metallurgical Engineering, Institut Teknologi Sepuluh Nopember, Jalan Teknik Kimia, Keputih, Surabaya, Jawa Timur 60111, Indonesia Abstract Air or water is potentially entered to the reactor core of HTGR - high temperature gas cooled reactors under normal or abnormal operation, so called air or water ingress. Therefore, the high stability and integrity of the materials used in the core is one of the critical issues for the development of HTGR which is directly influenced to the safety of the reactor. A nuclear graphite IG-110 has been tested at elevated temperature with air environment. The testing was carried out using Magnetic Suspension Balance to analyze the weight change with direct-monitoring. The testing was done up to 630 degree celcius of temperature for 420 minutes. Analysis of morphological and microstructure was performed using optical microscope, Scanning Electron Microscope-Energy Dispersive X-ray Sprectroscope and XRD X-Ray Diffractometer. The results showed that slightly change of the crystal size of the material structure and the trace of reaction between the surface material with oxygen have been observed. Nevertheless, weight change analysis showed that the weight-loss rate of the tested material was relatively low. Keywords: Nuclear, Graphite, IG-110, Oxidation, Microstructure Share Link | Plain Format | Corresponding Author (Abu Khalid Rivai)

145	Nuclear Science and Engineering	ABS-171
Microstructure Investigations of Phase Transformation in Cold Working Austenitic Stainless Steel AISI 316L Abu Khalid Rivai (a*), Nanda Shabrina (a), Bambang Sugeng (a), Sulistioso Giat Sukaryo (a) a) Center For Science and Technology of Advanced Materials, BATAN, Kawasan PUSPIPTEK Gedung 43, Tangerang Selatan, Banten 15314, Indonesia *rivai.abukhalid[at]batan.go.id Abstract Development of high temperature and corrosion-resistant materials is one of the key issues for the deployment of advanced nuclear reactors and also to accommodate the problem that occurred in the conventional reactor as the lesson-learned from Fukushima Daiichi nuclear reactor power plant accident. One of the high performance materials for that purpose is Duplex Stainless Steels (DSSs) which are a family of stainless steels. The metallurgical structure of the DSSs consists of two phases i.e. austenite (FCC: Face-Centered Cubic lattice) and ferrite (BCC: Body Centered Cubic lattice). Therefore, DSSs have properties characteristic of both austenitic and ferritic stainless steels. Furthermore, DSSs are also magnetic because of the ferrite phase existing. The cold working of AISI 316L at various percentage reduction of 5%, 10%, 15%, 25% and 38% have been done. Afterward, the sample was characterized using X-ray diffraction and Scanning Electron Microscope-Energy Dispersive Spectroscope to analyze the microstructure characteristics and phase transformation. The results showed that the percentage ferrite phase was increasingly growth related to the increasing of the percentage of cold working percentages value i.e. 2.7%, 8.3%, 21.8% 29.6% and 37.1%, respectively. Therefore, AISI 316L is potentially developed for the DSS material. Keywords: Duplex, steel, AISI 316L, austenite, ferrite Share Link | Plain Format | Corresponding Author (Abu Khalid Rivai)

146	Nuclear Science and Engineering	ABS-172
NATURAL RADIOCTIVITY OF ROCK AND POTENTIAL AVAILABILITY OF URANIUM-THORIUM MINERAL IN INDONESIA Adi Rahmansyah A.A1, Sidik Permana1,2, Wahyu Srigutomo,2 1Department of Nuclear Science and Engineering, Faculty of Mathematics and Natural Sciences, Bandung Institute of Technology, INDONESIA 2Department of Physics, Faculty of Mathematics and Natural Sciences, Bandung Institute of Technology, INDONESIA Abstract Radioactivity in rocks arises as a consequence of the presence of the radioactive elements uranium and thorium. These radioactive elements bond with other elements and form radioactive minerals that evolve on earth through a complex process that takes a very long time. In Indonesia, uranium and thorium mineralization are found in sandstone, metamorphic, volcanic types. volcanic, and intrusive. Generally, mineralization occurs due to hydrothermal processes caused by tectonic and volcanic activities. The potential for these radioactive minerals is spread from Aceh to Papua, with the highest concentrations found in Kalan (West Kalimantan), Mamuju (West Sulawesi), Sibolga (North Sumatra), and Bangka-Belitung. The main uranium minerals found are uraninite, davidite, coffinite, carnonite, while the main minerals for thorium are monazite and thorianite. Exploration of the potential content of nuclear minerals has been carried out by BATAN since 1970 until now. Interim results show that the potential reserves of uranium and thorium in Indonesia are 89,483 tU3O8 and 143,234 tTh, which is a combined number of hypotheticals, inferred, and measurable potentials. More detailed exploration needs to be carried out in order to produce measurable reserve figures and also expand exploration to other areas that also have the potential for the presence of uranium and thorium mineralization. Keywords: Potency, Uranium, Thorium, Indonesia Share Link | Plain Format | Corresponding Author (Sidik Permana)

147	Nuclear Science and Engineering	ABS-173
Nuclear Energy Contribution for Net Zero Emission and National Energy Mix 2060 in Indonesia Sidik Permana1,2*, Nuri Trianti2 and Adi Rahmansyah2 1Nuclear Physics and Biophysics Research Division, Department of Physics, 2Department of Nuclear Science and Engineering, Faculty of Mathematics and Natural Sciences, Institut Teknologi Bandung Jl. Ganesha 10, Bandung 40132, Indonesia *Email: psidik[at]fi.itb.ac.id Abstract Net zero emission ambition of Indonesian Government has strongly announcement to the public which is in line with the Paris Agreement that has been signed and ratified with other 164 countries across the globe to fulfil their commitment to reduce the greenhouse gas effect for their energy program which has the environmentally friendly energy sources. The government of Indonesia has stated that the new and renewable energy (NRE) should be utilized at least 23% by 2025 and 31% by 2050, as well as the net zero emission target in 2060 which only 100% of NRE for energy sector especially for power plant. In 2060, the estimated total demand market of about 1800 TWh which is consist of about 300 TWh of electric demand in the present status which will be required additional new energy supply of about 1500 TWh. This new additional energy which is about five times larger than the present energy which leads to more energy resources and alternative energy supplies are required. Meanwhile, fossil fuels as main producer will be reduced and NRE will be utilized more and it is increased gradually to maintain the energy demand as well as reducing the CO2 emission to the net zero target. In the present study, the contribution of each energy resources especially for the contribution of nuclear power plant (NPP) will be evaluated as a part of national energy mix. As announced by the national electric company (PLN) of Indonesia that NPP is estimated to be online in the national energy mix in 2040 by 10 GWe and it will be increasing gradually up to 2060. Keywords: zero emission, NRE, NPP, energy mix, Indonesia Share Link | Plain Format | Corresponding Author (Sidik Permana)

148	Nuclear Science and Engineering	ABS-174
Absorption Efficiency Analysis of Cotton Cloth Base Mask For Reducing Transmission Rate of Covid19 using PM2.5 Methods Detection Sidik Permana1,2*, Nuri Trianti2 1Nuclear Physics and Biophysics Research Division, Department of Physics, 2Department of Nuclear Science and Engineering, Faculty of Mathematics and Natural Sciences, Institut Teknologi Bandung Jl. Ganesha 10, Bandung 40132, Indonesia *Email: psidik[at]fi.itb.ac.id Abstract The spreading rate or transmission rate of COVID19 is very fast and now almost all country around the world is infected by this coronavirus. As a new type of coronavirus, it was identify that the structure of COVID-19 size of the virus of about 100 nm (nano-meter). The spreading droplet from coughs is between 1 meter of more to another person around him. Therefore, the important task is to make a physical distancing more than 1 meter from the sick. The transmission model of COVID-19 is different with other virus disease transmission such as through airborne or direct touch. The common transmission of COVID19 is from the spreading of the droplet through the air as well as the other media surface. The transmission of respiratory infection via droplet will have different dimensions or sizes. When the droplet size of particles in diameter are less than 5micro-m (<5micro-m), this size will be referred to as droplet nuclei and it can be the residue of dried respiratory aerosol that results from evaporation of droplet coughed or sneezed into the atmosphere or by aerosolization of infective material. Other droplet size is 5 to 10 micro-m or more, it can be referred as respiratory droplet or respiratory aerosols. One of the causes of very fast spreading transmission rate of COVID19 is coming from droplet transmission through the air which contain virus in small droplet size type. Rrecommendations that recommend airborne precautions for any situation involving the care of COVID-19 patients and consider the use of medical masks as an acceptable option in case of shortages of respirators (N95, FFP2 or FFP3). The other medical mask for general purposes in hospital or clinic is a surgical mask. A surgical mask, also known as a procedure mask, medical mask or simply as a face mask. Because of very rare and limited volume of mask for ordinary people as well as special mask for medical also becomes very limited. Keywords: COVID19, Transmission, Cotton Mask, PM2,5, absorption efficiency Share Link | Plain Format | Corresponding Author (Sidik Permana)

149	Nuclear Science and Engineering	ABS-175
Preliminary Neutronics Evaluation of 250 MWth MSR with FNaBe Type of Fuel Salt Cici Wulandari1, Abdul Waris2,*, Sidik Permana2, and Syeilendra Pramuditya2 1Department of Physics, Faculty of Mathematics and Natural Sciences, Institut Teknologi Bandung, Indonesia 2Nuclear Physics & Biophysics Research Division, Department of Physics and Department of Nuclear Science & Engineering Faculty of Mathematics and Natural Sciences, Institut Teknologi Bandung, Indonesia Jl. Ganesa 10 Bandung 40132, Indonesia *E-mail: awaris[at]fi.itb.ac.id Abstract FNaBe is one type of molten salts that has been recommended in the Molten Salt Fast Reactor (MSFR). For Molten Salt Thermal Reactor or commonly consider as Molten Salt Reactor (MSR), FLiBe and FLiNaK are considered as a coolant in MSR. Naturally occurring lithium is composed of two stable isotopes, 6Li and 7Li, where the latter being the more abundant (92.5% natural abundance). However, to utilize Li as part of coolant material in MSR, 7Li should be enriched to become 99.995% of abundance in the whole of Li. In this paper, we evaluate the neutronic performance of 250 MWth MSR with FNaBe fuel salt. The Japanese MSR FUJI-U3 has been selected as the basis of the evaluated 250 MWth MSR design with Thorium and Uranium as main fuel nuclides. Several neutronics parameters such as, fuel composition, effective multiplication factor, and conversion ratio will be discussed the full manuscript. Keywords: FNaBe- MSR- Neutronics- Thorium- Uranium Share Link | Plain Format | Corresponding Author (Abdul Waris)

150	Nuclear Science and Engineering	ABS-176
Conceptual Design of Small Modular Nuclear Reactor Thorium Based as a Solution for Energy Equity in Remote Area Muhamad Irfan (a*), Sidik Permana (a), Topan Setiadipura (b) (a) Nuclear Science and Engineering, Faculty of Mathematics and Natural Sciences, Institut Teknologi Bandung Jl. Ganesha No. 10, Bandung 40312 - Indonesia *irfan_aldrs[at]yahoo.com (b) Center of Nuclear Reactor Technology and Safety, National Nuclear Energy Agency of Indonesia Gd. 80 Kawasan Puspiptek Serpong Tangerang Selatan 15310 - Indonesia Abstract aaaSmall Modular Reactor (SMR) is one of many types of nuclear reactors which is very suitable and prospective to be applied to solve the problem of power supply deficit in remote area, as in many regions in Indonesia. SPINNOR is a concept of 4th generation of nuclear power reactor as SMR and Liquid Metal Fast Breeder Reactor (LMFBR) which can operate for a long life, about more than 15 years, without on-site refuelling. In this study, we will conduct study literature and analysis of the design of SPINNOR. The Uranium233-Thorium Nitride (U233,Th)N used as fuel, and it is expected that the reactor can operate for up to 20 years with maximum excess reactivity value < 2% dk/k. Keywords: Conceptual Design, Liquid Metal Fast Breeder Reactor, Small Modular Reactor, SPINNOR, Thorium Share Link | Plain Format | Corresponding Author (Muhamad Irfan)

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