JURNAL TEKNOLOGI REAKTOR NUKLIR TRI DASA MEGA
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The Study of Mechanical Failure in Helical Steam Generator of Nuclear Power Reactor
No full textThis research examines mechanical damage in helical steam generators, focusing on the causes, contributing factors, and impact of damage on the performance of the steam generator (SG). The research methodology involves analyzing various data sources, including scientific literature and previous nuclear industry experiences. The analysis results indicate that mechanical damage in helical SGs can be caused by factors such as thermal stress, pressure fluctuations, material wear, and design errors. Volumetric defects and leaks at pipe joints or welds are also potential issues. This study provides important insights into failure mechanisms and highlights the importance of routine maintenance and inspection to prevent more serious failures. With a better understanding of these issues, innovative solutions can be found to improve the performance and safety of helical steam generators in nuclear reactors
Experimental Study of The Influences of Inclination Angle and Heat Load on Loop Heat Pipe Thermal Performance
Full text linkThe utilization of nuclear power brings out a lot of benefits in fulfilling human power needs, however, the thermal incident caused by the failure of an active cooling system because of an earthquake followed by the tsunami such as on the Nuclear Power Plant at Fukushima Dai-Ichi Japan could be taken for lesson learn to keep improve nuclear installation operation safety aspects. Loop heat pipe (LHP) as an alternative cooling system technology could be utilized to handle thermal problems on nuclear installations. This research aims to know the influence of the inclination angle and heat load on the LHP thermal performance. The experimental investigation was performed with varying the inclination angle of 0°, 2.5°, and 5°, and heat load given at 60°C, 70°C, 80°C, and 90°C. LHP was used demineralized water working fluid with a 100% filling ratio. LHP was vacuumed on 2.666,4 Pa. The cooling air velocity in the condenser given by 2,5 m/s. The result of this experiment showed that LHP has the best thermal performance with the lowest thermal resistance of 0.0043°C/W. This result was obtained when the LHP operated with a 5° inclination angle and hot water as the heat load of 90°C. The conclusion from this research is showing better LHP thermal performance as the inclination angle increase on LHP because the steam speed that formed bigger, and condensate flows back to the evaporator faste
Advancements in Accident Tolerance Fuel: A New Horizon in Nuclear Safety
Full text linkAccident Tolerant Fuels (ATFs) represent a significant advancement in nuclear safety, offering the potential to mitigate the risks associated with nuclear reactor accidents. This paper provides a comprehensive overview of the development and current state of ATF technology, tracing its evolution and highlighting key technological milestones. Through an analysis of various case studies, we examine the practical application and performance of ATFs in real-world scenarios. Despite the promising capabilities of ATFs, their development and deployment are not without challenges. We delve into the technical, regulatory, and economic hurdles that must be overcome to realize the full potential of ATFs. Looking ahead, we explore the prospects of ATFs, discussing potential advancements and their implications for the nuclear industry. The findings of this paper underscore the transformative role of ATFs in enhancing nuclear reactor safety and charting a new horizon in nuclear technology
Dose Analysis of Boron Neutron Neutron Capture Therapy (BNCT) for Breast Cancer Based on Particle and Heavy Ion Transport Code System (PHITS) V.3.34
No full textKanker payudara merupakan salah satu jenis kanker yang paling banyak dijumpai, dengan angka kejadian dan kematian yang tinggi di seluruh dunia, termasuk di Indonesia. Boron Neutron Capture Therapy (BNCT) telah diformulasikan sebagai salah satu metode terapi radiasi yang menjanjikan dalam pengobatan kanker payudara karena kemampuannya dalam memberikan dosis tinggi pada target lesi dengan kerusakan minimal pada jaringan sehat. Penelitian ini bertujuan untuk menganalisis dosis BNCT pada kanker payudara dan mengeluarkan waktu penyalinan pada dua arah yaitu anterior-posterior (AP) dan lateral kiri (LLAT). Penelitian ini menggunakan alat simulasi PHITS versi 3.34 untuk mendefinisikan geometri kanker payudara dan organ di sekitarnya serta sumber radiasi yang digunakan. Fantom yang digunakan adalah wanita dewasa ORNL dengan tumor berukuran 2 cm. Sumber neutron yang digunakan adalah akselerator dengan berkas proton 30 MeV. Konsentrasi boron yang digunakan adalah 30, 60, 90, 120, dan 150 μg/g jaringan kanker. Penelitian ini menunjukkan bahwa semakin tinggi konsentrasi boron maka semakin cepat waktu penyinaran yang dihasilkan. Untuk teknik penyinaran AP, waktu penyinaran yang dihasilkan adalah 27,62 menit, 16,14 menit, 13,12 menit, 11,05 menit, dan 9,54 menit. Sementara itu, pada arah LLAT, waktu yang dihasilkan adalah 135,23 menit, 113,46 menit, 78,23 menit, 59,70 menit, dan 48,27 menit. Konsentrasi boron sebesar 150 μg/g dipilih sebagai konsentrasi optimal dalam simulasi ini karena menghasilkan waktu penyinaran yang singkat dari setiap arah penyinaran dan memastikan dosis yang aman bagi Organs at Risk. Pada teknik penyunaran AP, dosis yang diserap oleh kulit adalah 0,46 Gy, paru ipsilateral 1,01 Gy, paru kontralateral 0,16 Gy, hati 0,21 Gy, tulang rusuk 0,61 Gy, dan jantung 0,11 Gy. Sementara itu, pada teknik penyunaran LLAT, dosis yang diserap kulit sebesar 1,03 Gy, paru ipsilateral 2,19 Gy, paru kontralateral 0,72 Gy, hati 0,17 Gy, tulang rusuk 1,62 Gy, dan jantung 0,40 Gi
Data Visualization in The Human-Machine Interface of Reactor Protection System Simulator
Full text linkReactor Protection System (RPS) is essential to the functioning of nuclear power plants because it monitors important reactor parameters and triggers automated shutdowns as needed. The human-machine interface (HMI) of the RPS is crucial for giving operators the ability to efficiently monitor, analyze, and react to complicated data. The purpose of this study is to simulate the signal or data flow in the RPS of HTR-10, which is a high-temperature gas-cooled reactor (HTGR) with 10 MWth power. The HMI panels, as well as sensor input data, were generated using Python programming language. The HMI of RPS successfully and comprehensively presents the values of important sensor inputs and their trip setpoints (neutron flux, helium temperature, primary coolant pressure) both on panels and real-time graphs. Moreover, it also shows the reactor status (normal or trip) based on the existence of an initiation trip signal in the RPS. Alarm panels are generated when the reactor is tripped. The RPS simulator can be used for users or operators to understand the functionality of RPS, increase their awareness about the plant status, help them make decisions, and take appropriate actions to mitigate the anomalies
Computational Fluid Dynamics Simulation of Temperature Distribution and Flow Characterization in a New Loop Heat Pipe Model
Full text linkThe loop heat pipe (LHP) is considered for passive cooling systems in nuclear installations. A combined approach of simulation and experimentation is essential for achieving comprehensive knowledge of the LHP. Research on the LHP using Computational Fluid Dynamics (CFD) is necessary to understand phenomena that are challenging to ascertain experimentally. This study investigates the temperature distribution and flow characterization in a new LHP model. The method used in this research is simulation using CFD Ansys fluent software. In the simulation, the LHP has an inner diameter of 0.1016 m. This LHP features a wick made from a collection of capillary pipes without a compensation chamber. Demineralized water is used as the working fluid with a filling ratio of 100% of evaporator volume. The hot water temperature in the evaporator section is set at 70°C, 80°C, and 90°C. The temperature on the outer surface of the condenser pipe is determined using experimental temperature inputs. An inclination angle of 5° and an initial pressure of 12,100 Pa was applied to LHP. The CFD simulation results show that the temperature distribution profile under steady-state conditions in the loop heat pipe appears almost uniform. The temperature difference between the evaporator and condenser remains consistent. The flow of working fluid in the LHP is driven by buoyancy forces and fluid flow, allowing the working fluid in the LHP to flow in two phases from the evaporator to the condenser and then condensate from the condenser back to the evaporator. In conclusion, the temperature distribution and flow patterns in the LHP are consistent with common phenomena observed in heat pipes. This modeling can be used to determine the profiles of temperature distribution and flow in LHP of the same dimensions under various thermal conditions