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All Journal SIGMA EPSILON - Majalah Ilmiah Teknologi Keselamatan Nuklir Jurnal Teknologi Reaktor Nuklir Tri Dasa Mega
Puradwi Ismu Wahyono
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Computer Science & IT Energy Materials Science & Nanotechnology

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STUDI LITERATUR, INOVASI FITUR KESELAMATAN REAKTOR NUKLIR MELALUI PENGGUNAAN TEKNOLOGI FLUIDA NANO SEBAGAI FLUIDA PENDINGIN Puradwi Ismu Wahyono; Mulya Juarsa
SIGMA EPSILON - Buletin Ilmiah Teknologi Keselamatan Reaktor Nuklir Vol 13, No 2 (2009): Mei 2009
Publisher : Badan Tenaga Nuklir Nasional

Show Abstract | Download Original | Original Source | Check in Google Scholar | DOI: 10.17146/sigma.2009.13.2.2954

Abstract

Salah satu fiturkeselamatan reaktor nuklir adalah sistem pendinginan teras dalam keadaan darurat. Pendingin yangdipergunakan adalah air. Hasil studi literatur pada penelitian terdahulu tentang fluida nano, sebagai pendingindalam pendidihan kolam, menunjukkan meningkatnya CHF atau fluk kalor maksimum dan konduktivitas termalsebagai fungsi konsentrasi fluida nano. Peningkatan fluk kalor maksimum juga dialami pada eksperimenrewetting batang panas menggunakan air pada temperatur tinggi sebagai fungsi temperatur awal. Hasil studiliteratur memberikan ide inovasi fitur keselamatan reaktor nuklir melalui penggunaan teknologi fluida nanosebagai fluida pendingin. Pertimbangan yang diperlukan adalah CHF, konduktivitas termal, pengembanganfluida nano berkelas nuklir, dan kriteria fluida nano yang diperlukan. Aplikasi fluida nano sangat potensialsebagai sebuah inovasi fitur keselamatan reaktor nuklir. Inovasi tersebut perlu dikaji lebih lanjut dalam sebuahpenelitian untuk membuktikan bahwa perbaikan pertukaran kalor pada paska CHF menggunakan fluida nanoakan lebih menjamin proses pendinginan yang lebih cepat.
DEVELOPMENT OF EXPERIMENTAL POWER REACTOR (EPR) MODEL FOR SAFETY ANALYSES USING RELAP5 Andi Sofrany Ekariansyah; Muhammad Subekti; Surip Widodo; Hendro Tjahjono; Susyadi Susyadi; Puradwi Ismu Wahyono; Anwar Budianto
JURNAL TEKNOLOGI REAKTOR NUKLIR TRI DASA MEGA Vol 21, No 2 (2019): JUNI 2019
Publisher : Pusat Teknologi Dan Keselamatan Reaktor Nuklir (PTKRN)

Show Abstract | Download Original | Original Source | Check in Google Scholar | Full PDF (1853.799 KB) | DOI: 10.17146/tdm.2019.21.2.5449

Abstract

Pebble bed reactor design, classified as the high temperature gas-cooled reactor (HTGR), is currently being part of BATAN main program to promote nuclear energy by starting the Experimental Power Reactor (EPR) program since 2015. Starting from 2018, the detail design document has to be submitted into nuclear regulatory body for further assessment. Therefore results of design analysis have to be supplemented by performing a design evaluation, which can be achieved by developing the model of the EPR.  The development is performed using RELAP5/SCDAP/Mod.3.4 as the thermal-hydraulic analysis code validated for the light-water reactor having module for the pebble fuel element and non-condensable helium gas. Methodology of model development consists of defining the helium flow path inside the reactor pressure vessel, modelling of pebble bed core including its power distribution, and modelling of reflector components to be simulated under 100 % core power. The developed EPR model results in design parameters, which confirm the main thermal data of the EPR, including the pebble and reflector temperatures. The peak pebble temperature is calculated to be 1,375 °C, which requires further investigations in the model accuracy, since the reference values are around 1,015 °C, even it is below the pebble temperature limit. For safety analysis, the EPR model can be used under nominal core flow condition, which produces more conservative results by paying attention on the RELAP5 specific modules for the pebble bed-gas cooled system.Keywords: experimental power reactor, development, RELAP5, steady-state
Co-Authors Andi Sofrany Ekariansyah Anwar Budianto Hendro Tjahjono Muhammad Subekti Mulya Juarsa Surip Widodo Susyadi Susyadi