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All Journal SIGMA EPSILON - Majalah Ilmiah Teknologi Keselamatan Nuklir
Andi Sofrany Ekariansyah
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Computer Science & IT Energy

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ANALYSIS OF THE EFFECT OF ELEVATION DIFFERENCE BETWEEN HEATER AND COOLER POSITION IN THE FASSIP-01 TEST LOOP USING RELAP5 Andi Sofrany Ekariansyah; Hendro Tjahjono; Mulya Juarsa; Surip Widodo
SIGMA EPSILON - Buletin Ilmiah Teknologi Keselamatan Reaktor Nuklir Vol 19, No 1 (2015): Februari 2015
Publisher : Badan Tenaga Nuklir Nasional

Show Abstract | Download Original | Original Source | Check in Google Scholar | Full PDF (1072.747 KB) | DOI: 10.17146/sigma.2015.19.1.2895

Abstract

To understand the natural circulation phenomena on the passive residual heat removal system (PRHRS), development of a test section describing that phenomena in particular in the one phase condition is required. That test facility is named as FASSIP-01 in form of a vertically closed loop consisting of piping compo-nents, one cylinder tank featured with heater elements and one cooler. The heater tank will work as the heat source, and the cooler as the heat sink. This research is intended to support the experimental activity of the FASSIP-01 by conducting a simulation using the RELAP5/SCDAP/Mod3.4. Beside the standard loop configuration, the simulation is also conducted by varying the elevation of heater and cooler position to evaluate the best position resulting in the most optimal natural circulation. The results will be used as the comparison with the later performed experiment. The simulation result shows that for the case where the heater position is at the same level with the cooler position, the temperature distribution of the water after the heater and after the cooler are higher than the other two position. Looking at the natural circulation, that position results in the lowest mass flow. The position with the heater below the cooler will result in the best mass flow. On that position, only an optimiza-tion in the heat transfer surface area is needed to increase the heat transfer coefficient and secondary mass flow to remove the heat are needed to obtain more optimal performance of the water circulation caused by the density difference in the FASSIP-01 test loop.
EVALUASI KESELAMATAN REAKTOR TIPE PWR PADA KECELAKAAN PUTUSNYA JALUR UAP UTAMA Andi Sofrany Ekariansyah
SIGMA EPSILON - Buletin Ilmiah Teknologi Keselamatan Reaktor Nuklir Vol 15, No 1 (2011): Februari 2011
Publisher : Badan Tenaga Nuklir Nasional

Show Abstract | Download Original | Original Source | Check in Google Scholar | Full PDF (788.032 KB) | DOI: 10.17146/sigma.2011.15.1.2912

Abstract

Kecelakaan Putusnya Jalur Uap Utama (Main Steam Line Break Accident) merupakansalah satu jenis Kecelakaan Basis Desain (DBA). Kecelakaan ini perlu dianalisis dan dievaluasi dalam desainuntuk menetapkan persyaratan kinerja struktur, sistem dan komponen reaktor. Pada umumnya, efek serius yangperlu diperhatikan dalam kecelakaan ini adalah kemungkinan terjadinya kondisi return to power dan high localpower peaking yang dapat merusak batang bahan bakar. Berbeda dengan kecelakaan DBA lain, seperti LOCAmisalnya, kecelakaan ini dapat terjadi di dalam pengungkung dan dapat pula terjadi di luar pengungkung.Terdapat sekuensi dan dampak yang berbeda dari kedua skenario kecelakaan tersebut terhadap reaktor.Makalah ini mengevaluasi hasil simulasi dan perhitungan kecelakaan ini dengan menggunakan RELAP5/SCDAP/Mod3.2. Berdasarkan hasil evaluasi dapat diidentifikasi dan dibandingkan dampak-dampak kritisterhadap reaktor antara kejadian di dalam pengungkung dan di luar pengungkung.
Co-Authors Hendro Tjahjono Mulya Juarsa Surip Widodo