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January 15, 2025
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April 16, 2025
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Abstract
This study aims to understand the temperature distribution in the natural circulation system in the Intermediate Tank FASSIP-07 using the Computational Fluid Dynamics (CFD) method. Simulations were performed using Ansys Workbench R1 2024 software, with inlet temperature variations of 70°C, 80°C, and 90°C. The results showed that the highest temperature distribution was found at the inlet with a temperature of 90°C, while the outlet reached the lowest temperature at 70°C. This conclusion was obtained from the analysis of fluid flow driven by the buoyancy phenomenon due to differences in density. This study shows the potential for using a passive cooling system for nuclear reactors to improve safety in emergency conditions.
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This work is licensed under a Creative Commons Attribution-ShareAlike 4.0 International License.
Ciptaan disebarluaskan di bawah Lisensi Creative Commons Atribusi-BerbagiSerupa 4.0 Internasional.
How to Cite
ANALISIS DISTRIBUSI TEMPERATUR INTERMEDIATE TANK FASSIP-07 MENGGUNAKAN METODE COMPUTATIONAL FLUID DYNAMICS (CFD). (2025). Rekayasa Mekanika: Jurnal Ilmiah Teknik Mesin, 9(1), 33–37. https://doi.org/10.33369/rekayasamekanika.v9i1.39825
References
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[2] Broughthon JM, Kuan P, Petti DA, Tolman E. 2017. A Scenario On Three Mile Island Unit 2 Accident, Nuclear Technology: 87(1): 34-53.
[3] Samet JM, Chanson D. 2015. Fukushima Daiichi Power Plant Disaster. 1: 51.
[4] Juarsa M, Kiswanta,. Edy S, Joko PW, Ismu H, Puradwi IW. 2010. Fenomena Perpindahan Panas Pendidihan Berdasarkan Peristiwa LOCA dan Kecelakaan Parah. Indonesian Journal of Nuclear Science and Technology: 11(1): 1-12.
[5] Harjanto NT. 2008. Dampak Lingkungan Pusat Listrik Tenaga Fosil dan Prospek PLTN sebagai Sumber Energi Listrik Nasional. Jurnal Batan;1(1):39–50.
[6] BRIN. https://www.brin.go.id. diakses pada tanggal 20 september 2024
[7] Juarsa M, Antariksawan AR, Kusuma MH, Haryanto D, Putra N. 2018. Estimation of natural circulation flow based on temperature in the FASSIP-02 large-scale test loop facility. IOP Conference Series: Earth and Environmental Science:105(1):0–7.
[8] IAEA TECDOC. 2009. Passive Safety Systems and Natural Circulation in Water Cooled Nuclear Power Plants.
[9] Aroyyani M, Nuramal A, Hestiawan H. 2022. Simulasi Analisis Velocity Aliran Fluida Pada Tangki Reaktor Nuklir Menggunakan Metode Computational Fluid Dynamics (CFD). Rekayasa Mekanik: 6(2): 83–88.
[10] Ihsan S. 2018. Analisis Bentuk Aliran pada Kondensor Tipe Shell Dan Tube Menggunakan Simulasi CFD (Computational Fluid Dynamics), Jurnal JIEOM: 1(1):. 15–18.
References
Bastori I, Birmano MD. 2017. Analisis Ketersediaan Uranium di Indonesia untuk Kebutuhan PLTN Tipe PWR 1000 MWe. Jurnal Pengembangan Energi Nuklir Vol. 19, No. 2, (2017) 95-102.
[2] Broughthon JM, Kuan P, Petti DA, Tolman E. 2017. A Scenario On Three Mile Island Unit 2 Accident, Nuclear Technology: 87(1): 34-53.
[3] Samet JM, Chanson D. 2015. Fukushima Daiichi Power Plant Disaster. 1: 51.
[4] Juarsa M, Kiswanta,. Edy S, Joko PW, Ismu H, Puradwi IW. 2010. Fenomena Perpindahan Panas Pendidihan Berdasarkan Peristiwa LOCA dan Kecelakaan Parah. Indonesian Journal of Nuclear Science and Technology: 11(1): 1-12.
[5] Harjanto NT. 2008. Dampak Lingkungan Pusat Listrik Tenaga Fosil dan Prospek PLTN sebagai Sumber Energi Listrik Nasional. Jurnal Batan;1(1):39–50.
[6] BRIN. https://www.brin.go.id. diakses pada tanggal 20 september 2024
[7] Juarsa M, Antariksawan AR, Kusuma MH, Haryanto D, Putra N. 2018. Estimation of natural circulation flow based on temperature in the FASSIP-02 large-scale test loop facility. IOP Conference Series: Earth and Environmental Science:105(1):0–7.
[8] IAEA TECDOC. 2009. Passive Safety Systems and Natural Circulation in Water Cooled Nuclear Power Plants.
[9] Aroyyani M, Nuramal A, Hestiawan H. 2022. Simulasi Analisis Velocity Aliran Fluida Pada Tangki Reaktor Nuklir Menggunakan Metode Computational Fluid Dynamics (CFD). Rekayasa Mekanik: 6(2): 83–88.
[10] Ihsan S. 2018. Analisis Bentuk Aliran pada Kondensor Tipe Shell Dan Tube Menggunakan Simulasi CFD (Computational Fluid Dynamics), Jurnal JIEOM: 1(1):. 15–18.
[2] Broughthon JM, Kuan P, Petti DA, Tolman E. 2017. A Scenario On Three Mile Island Unit 2 Accident, Nuclear Technology: 87(1): 34-53.
[3] Samet JM, Chanson D. 2015. Fukushima Daiichi Power Plant Disaster. 1: 51.
[4] Juarsa M, Kiswanta,. Edy S, Joko PW, Ismu H, Puradwi IW. 2010. Fenomena Perpindahan Panas Pendidihan Berdasarkan Peristiwa LOCA dan Kecelakaan Parah. Indonesian Journal of Nuclear Science and Technology: 11(1): 1-12.
[5] Harjanto NT. 2008. Dampak Lingkungan Pusat Listrik Tenaga Fosil dan Prospek PLTN sebagai Sumber Energi Listrik Nasional. Jurnal Batan;1(1):39–50.
[6] BRIN. https://www.brin.go.id. diakses pada tanggal 20 september 2024
[7] Juarsa M, Antariksawan AR, Kusuma MH, Haryanto D, Putra N. 2018. Estimation of natural circulation flow based on temperature in the FASSIP-02 large-scale test loop facility. IOP Conference Series: Earth and Environmental Science:105(1):0–7.
[8] IAEA TECDOC. 2009. Passive Safety Systems and Natural Circulation in Water Cooled Nuclear Power Plants.
[9] Aroyyani M, Nuramal A, Hestiawan H. 2022. Simulasi Analisis Velocity Aliran Fluida Pada Tangki Reaktor Nuklir Menggunakan Metode Computational Fluid Dynamics (CFD). Rekayasa Mekanik: 6(2): 83–88.
[10] Ihsan S. 2018. Analisis Bentuk Aliran pada Kondensor Tipe Shell Dan Tube Menggunakan Simulasi CFD (Computational Fluid Dynamics), Jurnal JIEOM: 1(1):. 15–18.