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Pengembangan Sistem Pemantau Penggerak Batang Kendali Reaktor Serba Guna G. A. Siwabessy Berbasis LABVIEW Budi Supriyatman; Anwar Budianto; Heri Suherkiman
Reaktor : Buletin Pengelolaan Reaktor Nuklir Vol 14, No 2 (2017): Oktober 2017
Publisher : Direktorat Pengelolaan Fasilitas Ketenaganukliran (DPFK) RSG-GAS

Show Abstract | Download Original | Original Source | Check in Google Scholar | Full PDF (1304.247 KB) | DOI: 10.17146/bprn.2017.14.2.4078

Abstract

PENGEMBANGAN SISTEM PEMANTAU PENGGERAK BATANG KENDALI REAKTOR SERBA GUNA G. A. SIWABESSY BERBASIS LABVIEW. RSG-GAS telah melakukan pengembangan sistem instrumentasi yaitu  penggantian PLC Siemens tipe Simatic S5 dengan PLC Siemens tipe Simatic S7-300 pada sistem proses RSG-GAS. Salah satu kelebihan pemakaian PLC S7-300 adalah adanya fasilitas sistem pemantauan dan kendali yang dapat berkomunikasi dengan banyak jenis perangkat lunak. Tetapi pada saat ini peggunaannya belum dioptimalkan. National Instruments (NI) OPC Server menyediakan sebuah antarmuka untuk berkomunikasi dengan berbagai perangkat. Kombinasi NI OPC Server dan LabVIEW menyediakan satu platform untuk memberikan pengukuran berkinerja tinggi dan kontrol untuk kedua sistem instrumentasi baru dan yang sudah ada. Server NI OPC terhubung melalui OPC Client di data logging LabVIEW dan Modul Supervisory Control (DSC) sehingga memungkinkan dapat mengembangkan sistem HMI/SCADA secara total dengan PLC, Programmable  Automation Controller (PACs) dan sensor. Pengembangan sistem pemantau penggerak batang kendali RSG-GAS berbasis LabVIEW menampilkan indikator-indikator penggerak batang kendali RSG-GAS seperti yang ada pada meja pengatur RSG-GAS yang dilengkapi dengan kemampuan dokumentasi data pemantauan untuk keperluan analisa hasil operasi.
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