Study of the Impact of Nuclear Power Plants (NPP) and NuScale Reactors on Economic and Environmental AspectsWijaya, Kevin
doi: 10.1088/1757-899x/1330/1/012003pmid: N/A
Nuclear Power Plants (NPPs) are one type of power plant that can produce large amounts of electricity and do not produce carbon. Although when operating, NPPs can compete with power plants from other energy sources, they require quite large capital costs. In addition, there have been cases of nuclear accidents that have an impact on the environment. Therefore, this article discusses the economic and environmental analysis of the existence of NPPs. In addition, the NuScale Reactor is also analyzed from the design and development, seawater desalination, and the impact of NuScale on the economy and the environment. From the results of the study, it was found that NPPs require large capital costs but when operating they tend to be smaller, NPPs can also open up jobs from various sectors, have a significant impact on environmental objects such as water quality, soil, air, ecosystems, and habitats. Also obtained are design features that are only owned by NuScale and can answer the Fukushima disaster problem. Then, information was obtained that there are three desalination and reverse osmosis (RO) processes that are more efficient in terms of economy and produce clean water, while if water quality is desired, the multi-effect distillation (MED) process can be used.
Analysis of Radionuclide Content in Soil Samples Using the X-Ray Fluorescence Spectroscopy (XRF) MethodHumolungo, Ismail; permana, Sidik; Abdullah, Adi R.A; , Zulfahmi; Seno, Haryo; Maulana, Alan
doi: 10.1088/1757-899x/1330/1/012020pmid: N/A
The high average value of natural gamma radiation dose rate in Mamuju Regency indicates that the uniqueness is related to the high concentration of radioactive elements of Uranium, Thorium, and Potassium deposited in the rock. In this study, X-Ray Fluorescence tests were carried out with Energy Dispersive X-Ray Fluorescence equipment on 5 soil samples from Mamuju Regency. Measurements were made on powder and pellet specimens. The results showed that the average concentration of radioactive elements uranium (U) was 712.17 ppm and 3581.45 for Thorium (Th), while for Potassium (K) was 9127.75 ppm. The thorium element appears to be more dominant with the Th/U ratio reaching 3.99 which is higher than the average Th/U ratio in the Earth’s crust of 3.70. A positive correlation between U and Th was obtained with a correlation coefficient value of 0.60, and a positive correlation was also shown by the relationship between U and Th, indicating the enrichment of U along with the enrichment of Th. Analysis of XRF data and dose rate data shows that there are two locations that show a very close relationship between the dose rate and the concentration of radioactive elements in the sample, while in other samples the influence of land use into gardens or highway strips affects the measured dose rate.
Study of Prospecting NPP Cogeneration as District Heating and Cooling in IndonesiaSetiawan, A Muksin Aji; Permana, Sidik; Setiadipura, Topan
doi: 10.1088/1757-899x/1330/1/012007pmid: N/A
Metropolitan areas like Jakarta are often associated with dense populations and significant energy consumption challenges. During working hours, the city sees the movement of up to 4 million people, creating a distinct energy demand pattern compared to surrounding satellite areas. Energy usage peaks during the summer months due to the high demand for air conditioning, highlighting the need for a stable electricity supply. Jakarta’s current reliance on coal as its primary energy source becomes problematic when supply chains are disrupted or coal becomes economically unsustainable. Moreover, coal usage contributes to long-term environmental degradation. In alignment with the government’s target of achieving net-zero carbon emissions, there is a growing urgency to adopt renewable energy alternatives. Nuclear power presents itself as a viable solution for Indonesia, given its high energy output. The cogeneration capability of Nuclear Power Plants (NPPs) can be utilized for district heating and cooling (DHC), decreasing the city’s reliance on fossil fuels, particularly for cooling. This shift could significantly cut down on air pollution caused by fossil fuel combustion, thus enhancing air quality in Jakarta. This study explores the feasibility of integrating NPPs in major Indonesian cities, factoring in geographical, demographic, economic, and environmental aspects. Ultimately, the initiative aims to help Jakarta progress toward a cleaner and more sustainable urban environment.
Assessment of Material Attractiveness in Light Water-Based Reactors: Evaluating Plutonium Isotope Composition and Burnup Impact on Proliferation RiskNasyidiah, Fungky Iqlima; Aimon, Akfiny Hasdi
doi: 10.1088/1757-899x/1330/1/012017pmid: N/A
The assessment of nuclear safety and the potential risks associated with proliferation is a critical area of research in the context of nuclear energy utilization. This study focuses on evaluating the Material Attractiveness (ATTR) in several light water-based reactor designs, specifically NuScale, ESBWR, BWRX-300, and PWR, both during reactor operation and post-operation. The analysis employed Origen 2.2 for modeling radioactive decay and MCNP4C for assessing material attractiveness. The findings reveal an increase in the production of plutonium isotopes, with the exception of Pu-239, which decreases as a result of the fission. Initially, the Pu-240 composition across all four reactors is classified as Super-grade plutonium. However, with increased burnup, the Pu-240 composition transitions to a reactor-grade plutonium level. At the initial of irradiation, the ATTR values were determined to be 0.19 for the ESBWR, 0.20 for the PWR, 0.16 for the BWRX-300, and 0.21 for NuScale, categorizing them within the weapon-grade range. By the end of reactor operation, these values had significantly decreased, with ESBWR at 0.0125, PWR at 0.0148, BWRX-300 at 0.0111, and NuScale at 0.0133, placing them in the un-usable grade category. This marked reduction in ATTR values, correlated with increased burnup, indicates an effective decrease from weapon-grade to un-usable grade by the end of the reactor^s operational period. This trend is primarily influenced by the increased production of isotopes Pu-238, Pu-240, Pu-242, and the corresponding decrease in Pu-239, the primary fissile material.
Evaluation of a PVT-Based Scintillation Detector as a Cost-effective Early Detection Solution in Nuclear Reactor Safety SystemsYasmint, Imam Ghazali; Wulandari, Cici; Tursinah, Rasito; Amatullah, Amila; Humolungo, Ismail; Variastuti, Marisa; , Zulfahmi
doi: 10.1088/1757-899x/1330/1/012022pmid: N/A
The safety measures for nuclear reactors are constantly advancing in line with the progress in utilizing nuclear reactors as power sources. Furthermore, the capabilities of early detection systems in nuclear reactors are always evolving to provide the most efficient detectors. The rise of gamma radiation levels serves as an indicator in the safety system of nuclear reactors, and it refers to the gamma radiation detector. An outcome of the advancement of gamma radiation detectors is the creation of detectors that possess exceptional capabilities but come with an expensive cost. Poly Vinyl Toluene (PVT) plastic can function as a gamma detector and is cost-effective. This study aims to investigate the possibility of utilizing PVT-based scintillation detectors as a cost-effective solution for incorporating early detection capabilities into nuclear reactor safety systems. The work involved the characterization of PVT-based scintillation detectors, followed by a comparison with commercially available detectors. This research is concerned with the efficiency of the detector.
Preliminary Numerical Investigation of Cooling Fins Feature in the Frozen Salt Melting PerformanceHidayati, Anni Nuril; Mustari, Asril Pramutadi Andi; Huljanah, Yulia Mifftah; Widiawati, Nina
doi: 10.1088/1757-899x/1330/1/012006pmid: N/A
The opening time of the freeze plug safety feature in a molten salt reactor is a crucial aspect that must be carefully considered. This relates to the reactor core’s drainage during a blackout or abnormal temperature rise due to a Loss of Coolant Accident (LOCA) while in operation. This study analyses the impact of varying the geometry of the distance between the freeze plug and cooling fins on the opening time. Calculations were performed using a particle-based Lagrangian numerical simulation called MPS, Moving Particle Semi-implicit. The calculations were conducted using two-dimensional geometry, with the initial design being an inline arrangement. The MPS improvement involves forced convective heat transfer between the liquid fuel, the freeze plug, and the cooling fins. At the same time, conductive calculations were performed among the freeze plug particles during melting. The results show that a larger distance between the fin and plug has an insignificant effect on the opening time. This study is essential to determine the variations that yield optimal values for supporting the safety system of molten salt reactors.
Assessment of Transfer Factors for Natural Radionuclides and Radiocesium from Soil-to-Plant and Plant-to-Cow’s Milk on a Cattle Farm in LembangYasmint, Imam Ghazali; Waris, Abdul; Pudjadi, Eko
doi: 10.1088/1757-899x/1330/1/012021pmid: N/A
Human populations are exposed to both natural and artificial radiation. This research aims to measure the radioactivity of natural and artificial radionuclides in soil, grass, and cow’s milk to determine the possible transfer of radionuclides through the food chain in Lembang, West Java, Indonesia. The samples were obtained from a nearby cattle farm and analyzed with an ORTEC gamma spectrometer with an HPGe detector to determine the radionuclides, including 226Ra, 232Th, 40K, and 137Cs. Analysis indicated that the radioactivity concentration in soil is below the world average. Transfer factor analysis revealed that 40K possesses the highest transfer factors from soil to plant and from plant to milk, validating the results of previous studies. In addition, 137Cs were detected in grass and soil but not in milk samples, indicating no further transmission through the food chain. The findings indicate radionuclide transfer mechanisms and show a low radiation risk level in the study area.
A Brief Comparison of Indonesian Prospective Nuclear Fuel CyclesMulyana, Dany
doi: 10.1088/1757-899x/1330/1/012014pmid: N/A
A brief comparison study on fuel cycles of four prospective Indonesian power reactors has been completed. The study oversees 160 MWt NuScale Small Modular Reactor (SMR), 10 MWt Reactor Daya Eksperimental (RDE-10), 40 MWt Pembangkit Listrik dan Uap Panas Industri (PeLUIt-40) and Thorcon’s TMSR-500. Both RDE-10 and PeLUIt-40 were fueled with 17wt% HALEU while the other two were fueled by 4.95wt% LEU, without thorium. The study was based on a set of data generated through Monte Carlo reactor physics simulation using OpenMC. The study found that NuScale SMR is the least 235U consumer by 0.84 g.MW−1 d−1 while the RDE-10 is the most 235U consumer by 0.97 g.MW−1 d−1. The simulation results show that TMSR-500 is the most uranium consumer by 1.41 g.MW−1 d−1 while the uprating of RDE-10 to PeLUIt-40 makes PeLUIt-40 as the least uranium consumer by 1.14 g.MW−1 d−1. As the least uranium consumer, both RDE-10 and PeLUIt-40 provide the highest attainable discharged fuel burnup of extractable energy of about 146 GWd/MTU. Assuming a one batch depletion scheme, NuScale SMR, RDE-10, PeLUIt-40 TMSR-500 has fuel consumption cycles in 2,210 days, 2140 days, 550 days, and 320 days, respectively.
Computed radiography method for non-destructive testing to characterize cooling piping in research reactor G.A SiwabessySutanto, Jepri; Hanurajie, Baskan; Sumirat, Iwan; Mustari, Asril P.A.
doi: 10.1088/1757-899x/1330/1/012016pmid: N/A
A radiographic test is one of the NDT methods used to verify the material (non-destructive testing). It utilizes ionizing radiation, such as X-rays or gamma rays, to create detailed images that reveal hidden flaws, defects, discontinuities, or anomalies. A radiographic test method commonly checks welding connections, fabrication, forging, and casting. Radiography NDT technique is used across diverse sectors, including manufacturing, aerospace, infrastructure, energy, and even research reactors or nuclear power plants (NPP). This study will discuss the piping in the research reactor in South Tangerang, i.e., G.A. Siwabessy (RSG-GAS), in the context of maintenance and inspection. Industrial digital radiography substitutes conventional film radiography and is replaced by imaging plate (IP). Parameters such as SNR and CNR and basic spatial resolution (SRb) must be considered and understood. Digital radiography is currently more widely used in addition to the short process and interpretation of results with up-to-date software developments. The linear indication is attached to the result of the interpretation. The linear indication’s orientation, size, and shape recommendations can provide valuable information to the nuclear energy research organization while replacing or substituting the piping. Image interpretation results were obtained to provide recommendations for improvements by standards and regulations. Other NDT methods are needed to compare the results.
Comparison of Fission and Non-Fission Methods in Mo-99 Radioisotope ProductionSalsabila, Dhiya Salma; Rohanda, Anis
doi: 10.1088/1757-899x/1330/1/012024pmid: N/A
The utilization of the G.A. Siwabessy Multipurpose Reactor (RSG-GAS) includes the production of radioisotopes. Among the radioisotopes produced by RSG-GAS is Mo-99. The Mo-99 radioisotope is used in the production of Technetium-99m (99mTc), which is used in diagnostic imaging in the medical field. There are two ways to produce the Mo-99 radioisotope. First, with a fission scheme using Low Enriched Uranium (LEU) in the form of UO2. Second, with a non-fission scheme by irradiating MoO3 samples. The aim of this study is to analyze the production results of radioisotopes using the fission scheme compared to the non-fission scheme using the ORIGEN 2.1 program. In this study, an MoO3 sample weighing 8.753 grams is compared to UO2 weighing 8.753 grams with the composition: U-235 1.508 grams, U-238 6.206 grams, and O-16 1.039 grams. Then, variations in the irradiation position in the reactor were made, namely at the Central Irradiation Position (CIP) at locations E7 and D6, as well as the Irradiation Position (IP) with reactor power of 5, 15, and 30 MWt. The calculation results show that at CIP-D6 with a power of 30 MWt, the production result of the non-fission scheme is 7.05 Ci. Meanwhile, the production result of the fission scheme under the same conditions is 797.10 Ci. This is due to the better ability of UO2 to capture neutrons needed in nuclear reactions, as well as having more uranium isotopes that easily undergo neutron fission. Therefore, for Mo-99 production, it is recommended to use the fission scheme.