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The aim of the research is to analyze a study of quality of the development of Sultan Hasanuddin International airport through the concept of the Smart Airport. The methodology of research using descriptive quantitative and qualitatifve research. The descriptive quantitative analysis in this research use the scale of likert and path analysis with the help of SmartPLS software. The results of the research showed that the quality and performance level of services of Sultan Hasanuddin International airport Makassar based on the quality and performances services attributes, namely reliability, responsiveness, assurance, empathy and tangible and the level of customer satisfaction. the quality of airport development services indicate a significant indirect or direct significant effect on customer satisfaction. The value of r-square on the performance of airport development services is 0.823 > 0.70 at the level of customer satisfaction 0.6278 > 0.70, it can be concluded that the variables and indicators are reliable because they fulfill of requirements > 0.70. In this case the T-value < 1.96 and P-value < 0.05. Thus, it can be concluded that the X4 variable has not significant effect on the Y variable with its indicators. Based on the results of the research, it can be concluded that the quality and performance of airport development services through a conceptual approach Smart Airport significant effect on the level of customer satisfaction. Hoped that in the future airport development will be further improved considering that the Sultan Hasanuddin International Airport in Makassar will be planned to go to Makassara erocity with the aerotropolis concept and Smart Airport concept as a supported of technological service innovation that provides basic infrastructure so that all activities it can be well connected.

In research reactor, gamma heating deposited in the samples is an important issue because it is related to the samples and the reactor operational safety. Multi Purpose Reactor (MPR) 30 MWth or its called Reaktor Serba Guna G.A. Siwabessy (RSG-GAS) is a research reactor that play a role as a place to irradiate various target material type. RSG-GAS has been operating since 1987 and the last measurement of gamma heating in the core was conducted around twenty years ago in oxide core. In 1996, RSG-GAS core was converted from oxide fuel type to silicide fuel type. The purpose of the conversion are to improve the performance and efficiency of RSG-GAS. As part of RSG-GAS irradiation facilities safety analysis, the gamma heating measurement was re-conducted in order to obtain latest data as benchmark data in silicide core. This paper presents the results of gamma heating measurement of LEU silicide RSG-GAS core in Central Irradiation Position (CIP) at 15 MW and 30 MW power level using gamma calorimeter. There were four types of calorimeter used, which were calorimeter with graphite (C) sample, iron (Fe) sample, aluminum (Al) sample and zirconium (Zr) sample. Gamma heating calculations using GAMSET code were performed to verify the measurement results. The measurement results are lower than the GAMSET results and the gamma heating value increases in proportion to the increase of calorimeter sample atomic number. This results are corresponds to gamma heating benchmarking results of RSG-GAS oxide core. Several optimization efforts both measuring and modeling with GAMSET were conducted as an evaluation and justification of the results. The best optimization results are achieved using the maximum value of the measurement and adjusting the power peaking factor (PPF) distribution. The calculated gamma heating value optimization results at 15 MW power are 2.78 W/g (C sample), 2.74 W/g (Al sample), 3.36 W/g (Fe sample) and 4.60 W/g (Zr sample) while at 30 MW power level are 5.57 W/g (C sample), 5.49 W/g (Al sample), 6.75 W/g (Fe sample) and 9.23 W/g (Zr sample). The best optimization results serve as a benchmark data for developing new gamma heating calculation programs based on 18 gamma energy groups.

A pulse height analyzer (PHA) is used to measure the frequency distribution of the signal output height of an event detector. However, the typical PHA algorithm has limitations in measurement; it cannot distinguish multiplet due to coincidence and singlet pulse. Coincidences will pile up the signals that make the pulse height value higher than it should be. Therefore, this study has developed a simple algorithm to calculate pulse height distribution with coincidence correction (PHA-CC). The developed algorithm firstly identified the coincidence pulse by considering its pulse width. The result shows that the developed algorithm could successfully distinguish multiplet and singlet pulses. The significance of pulse height distribution measured by the PHA-CC compared to regular PHA was also discussed in this paper.

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.

Molten salt has attracted the attention of researchers, especially as a coolant because of its characteristics. This study aimed 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 was used to solve governing equations. Experimental data from several references were used as input data in modelling. The loop was 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 was also carried out in modelling. The modelling results showed a 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.

The comparison of four blanket modules in DEMO made up the optimization material having a reasonable requirement as blanket material in this study. Either neutron flux distribution in blanket material or material endurance under neutron irradiation, from four modules, the WCLL has a high tolerance neutron distribution and the best neutron irradiation endurance. Furthermore, many suggestions closed to the statement to use the benefits of water coolant and lithium lead (compose Li-6) as a material component in the blanket.

One of the drying machines that is commonly used by in industry is a rack-type dryer. However, the rack-type drying machine has generally fairly low efficiency. A rack-type dryer has been designed which was equipped with a hybrid mechanism, but is its performance not yet known when it is controlled by an expert control system. The purpose of this research was to produce an expert control system that can be applied to a rack-type dryer with a hybrid system mechanism which can improve the performance of the dryer. The research includes the development of expert rules applied to the control system and a series of tests was carried out using 10 kg of fresh sago starch. The test results show that the drying air temperature did not show any overshoot and short settling time, drying temperature is relatively stable and there was no steady state error. The drying rate of fresh sago starch can be increased by using the hybrid system. The use of electric power with the hybrid system was lower (5.78 kWh) compared to that of non-hybrid (6.88 kWh) or a reduction of about 16% compared to the non-hybrid system. Thermal efficiency of the rack-type dryer with the expert control system was about 36%.

Series of MPS simulations have been conducted using two-dimensional geometry. The simulation was based on Sudha’s experiment (2018) about initial velocity variations on molten Wood’s Metal (WM). The molten WM would be flowed through nozzle with the diameter was 6 mm. It would impinge to the Woods Metal Plate (WMP) which 270 mm below the nozzle. The WMP diameter was 470 mm. The temperature of molten WM and WMP were set at 573 K and 300 K, respectively. The initial velocity of molten WM was varied at 0.327 m/s, 0.397 m/s, 0.498 m/s in the y-negative direction. The simulation was calculated by using 2D MPS with additional procedures such as heat transfer calculation and defining a new type of wall particle. The results showed some different spread patterns, leading edge and phase fraction change for each initial velocity. It can be concluded that with varying the initial velocity will affect on the radial spread pattern but not so much effect occurs on the phase volume fraction change.

Variation of solid ceramic breeding might be one of the excellent candidates in a fusion reactor. The LiAlO2, Li4SiO4, Li2O, and Li2ZrO3 show pretty good requirements in tritium breeding capability and thermodynamic behavior. Especially for LiAlO2 and Li2ZrO3, in which they could be possible to breed without neutron multiplying needed as blanket used generally in order to reach the self-sufficiency reactor. So that, it makes up the material could be possible as high-estimation breeder material.

An advanced nuclear reactor Generation IV, called Molten Salt Reactor (MSR), has been developed with Thorium utilization for a sustainable energy system. In this paper, the study is focused in the neutronic calculation of 250 MWt/100 MWe MSR with Thorium-Plutonium (Th-Pu) fuel salt for 5 years time operation. Fuel salt is composed of a eutectic FLiBe, Th, and Pu, as a coolant, fertile, and fissile nuclide, respectively. Pu loaded is a weapon-grade which consist of 238Pu, 239Pu, 240Pu, 241Pu, 242Pu, and 241Am. The reactor is operated in the thermal energy range and moderated by the graphite. The reactor design is calculated in neutronic terms with program code CITATION in SRAC 2006 with JENDL 4.0 as a nuclear data library. The result shows some neutronic parameter changes with increasing Plutonium loaded and the reactor criticality is obtained for 5 years by minimal loaded of PuF4 of 2.41%mol. The utilization of Plutonium is described as a capability of MSR in burning a high-level waste of nuclear and radioactive isotopes. This system can be dedicated to future cleaning energy production in a nuclear reactor.

The problem of food waste is increasing as food needs increase as a source of human protein. Therefore, biogas conversion can also answer the problem of household food waste treatment. The purpose of this study is to find out the producing of biogas from a mixture of food waste and liquid waste tofu in anaerobic biodegester at thermophylic temperature. The manufacture of biogas in this study using batch feeding, which is a type of digester that replenishes organic matter is done once full and then waited until biogas is produced. The manufacture of biogas is carried out for 5 weeks. The observed parameters are COD, BOD, TS, VS, and the resulting volume of biogas. From the observations obtained that, by varying substrate can decrease COD, BOD, TS, while substrate temperature can increase VS. The volume of biogas produced in the mixture of liquid waste tofu 60% and food waste 30% is 22.600 ml. The results showed that the percentage of substrate from the mixture of food waste with liquid waste tofu had an effect on increasing biogas production.

Finite element method with linear triangular shape function was used to numerically investigate steady state heat conduction in composite layer. This method divides each layer into a number of small elements. By defining elements, local node, global node, and temperature boundary conditions, an element coefficient matrix can be formed. Element coefficient matrix needs to be assembled to form a global coefficient matrix. The solution of the global coefficient matrix will provide the temperature value at each node. In this research, variations of the thermal conductivity value and temperature boundary conditions are applied. The results of the study will show the effect of different thermal conductivity value against temperature gradient.