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All Journal SIGMA EPSILON - Majalah Ilmiah Teknologi Keselamatan Nuklir Urania Jurnal Ilmiah Daur Bahan Bakar Nuklir
Hery Adrial
Pusat Teknologi dan Keselamatan Reaktor Nuklir - BATAN
Computer Science & IT Energy Materials Science & Nanotechnology

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ANALISIS PERHITUNGAN DISTRIBUSI TEMPERATUR TERAS DAN REFLEKTOR REAKTOR DAYA EKSPERIMENTAL Suwoto Suwoto; Hery Adrial; Topan Setiadipura; Zuhair Zuhair
SIGMA EPSILON - Buletin Ilmiah Teknologi Keselamatan Reaktor Nuklir Vol 20, No 2 (2016): November 2016
Publisher : Badan Tenaga Nuklir Nasional

Show Abstract | Download Original | Original Source | Check in Google Scholar | Full PDF (1412.941 KB) | DOI: 10.17146/sigma.2016.20.2.3514

Abstract

Reaktor Daya Eksperimental (RDE) adalah salah satu jenis reaktor temperatur tinggi berpendingin gas helium yang pengoperasiannya harus memenuhi batas standar keselamatan operasi, khususnya dari aspek temperatur, sehingga penelitian tentang dis- tribusi temperatur pada bahan bakar yang berada di teras dan reflektor reaktor sangat penting untuk dilakukan. Program PEBBED6 dirancang khusus untuk reaktor jenis PBR (Pebble Bed Reactor) ber- bahan bakar jenis bola dan dapat menghitung parameter neutronik dan distribusi temperatur pada teras reaktor maupun reflector dalam teras RDE menggunakan fraksi packing 61%. Perhitungan dan pemrosesan spektrum tampang lintang menggunakan program COMBINE dan perhitungan distribusi temperatur pada bahan bakar pebble dan daerah reflektor dilakukan dengan menggunakan modul THERMIX-VSOP yang sudah terintegrasi dengan program PEBBED6. Hasil perhitungan temperatur permukaan pebble pada bagian tengah dan atas teras aktif untuk tiga ketebalan reflektor 100 cm, 150 cm dan 200 cm masing-masing adalah 646,50 oC dan 761,30 oC, sementara temperatur permukaan pebble pada teras bagian tengah dan atas paling dekat dengan reflektor samping adalah 601,40 oC dan 695,80 oC. Sedangkan temperatur pada reflektor sisi samping bagian tengah dan atas terluar untuk ketebalan 100cm masing-masing adalah 413,20 oC dan 438,30 oC, sementara temperatur pada ketebalan reflektor 150 cm dan 200 cm adalah 340,80 oC dan 353,90 oC. Secara keseluruhan, hasil perhitungan menghasilkan distribusi temperatur permukaan bahan bakar teras dan reflektor yang berada pada nilai di bawah batas keselamatan temperatur yang dipersyaratkan. 
EVALUATION OF RADIATION DOSE RATE OF RSG-GAS REACTOR Amir Hamzah; Hery Adrial; Subiharto Subiharto
Urania : Jurnal Ilmiah Daur Bahan Bakar Nuklir Vol 24, No 3 (2018): Oktober, 2018
Publisher : website

Show Abstract | Download Original | Original Source | Check in Google Scholar | DOI: 10.17146/urania.2018.24.3.4909

Abstract

EVALUATION OF RADIATION DOSE RATE OF RSG-GAS REACTOR. The RSG-GAS reactor has been operated for 30 years. Since the nuclear reactor has been operated for a long time, aging process on its components may occur. One important parameter for maintaining the safety level of the RSG-GAS reactor is to maintain radiation exposure as low as possible, especially in the working area. The evaluation results should be able to demonstrate that the radiation exposure of the RSG-GAS is still safe for workers, communities and the surrounding environments. The purpose of this study is to evaluate radiation exposure in the working area to ensure that the operation of RSG-GAS is still safe for the next 10 years. The scope of this work is confirming the calculation results with the measured radiation dose in the RSG-GAS reactor working area. Measurement of radiation exposure is done by using the installed equipments at some points in the RSG-GAS working area and a portable radiation exposure measurement equipment. The calculations include performance of a modeling and analysis of dose rate distribution based on the composition and geometry data of RSG-GAS by using MCNP.  The analysis results show that the maximum dose rate at Level 0 m working area of RSG-GAS reactor is 3.0 mSv/h with a deviation of 6%, which is relatively close to the measurement value. The evaluation results show that the dose rate in RSG-GAS working area is below the limit value established by the Nuclear Energy Regulatory Agency of Indonesia (BAPETEN) of 10 mSv/h (for the average effective dose of 20 mSv/year). Therefore, it is concluded that the dose rate in RSG-GAS working area is safe for personnel..Kata kunci: dose rates, RSG-GAS, radiation safety, MCNP.
Co-Authors Amir Hamzah Subiharto Subiharto Suwoto Suwoto Topan Setiadipura Zuhair Zuhair