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All Journal Jurnal Pengembangan Energi Nuklir Urania: Jurnal Ilmiah Daur Bahan Bakar Nuklir
Sri Kuntjoro
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Decision Sciences, Operations Research & Management Earth & Planetary Sciences Electrical & Electronics Engineering Energy Engineering Environmental Science Industrial & Manufacturing Engineering Social Sciences

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AKTIVITAS DAN KONSEKUENSI DISPERSI RADIOAKTIF UNTUK DAERAH KOTA DAN PEDESAAN Pande Made Udiyani; Sri Kuntjoro; Jupiter Sitorus Pane
Jurnal Pengembangan Energi Nuklir Vol 17, No 2 (2015): Desember 2015
Publisher : Pusat Kajian Sistem Energi Nuklir, Badan Tenaga Nuklir Nasional

Show Abstract | Download Original | Original Source | Check in Google Scholar | DOI: 10.17146/jpen.2015.17.2.2603

Abstract

ABSTRAKAKTIVITAS DAN KONSEKUENSI DISPERSI RADIOAKTIF UNTUK DAERAH KOTA DAN PEDESAAN. Konsekuensi karena lepasan kontaminan radioaktif oleh manusia dipengaruhi oleh banyak faktor seperti besarnya aktivitas kontaminan yang tersebar dan kondisi lingkungan. Kondisi lingkungan meliputi kondisi meteorologi, kontur tapak, dan pathway kontaminan ke manusia. Tujuan penelitian ini adalah analisis aktivitas dan konsekuensi radionuklida waktu paruh panjang akibat kecelakaan di daerah perkotaan dan pedesaan. Tujuan khusus adalah menghitung aktivitas dispersi udara dan deposisi permukaan, prediksi laju dosis dan risiko yang ditimbulkan untuk daerah perkotaan dan pedesaan sebagai fungsi lokasi. Metode yang digunakan adalah simulasi estimasi konsekuensi dari dispersi produk fisi di atmosfer akibat kecelakaan terpostulasi Beyond Design Basis Accident, BDBA. Perhitungan dilakukan untuk lepasan radioaktif akibat kecelakaan PWR 1000 MWe yang disimulasikan untuk area pedesaan dan perkotaan Tapak Bojanegara-Serang. Hasil analisis aktivitas dispersi udara dan deposisi permukaan untuk area pedesaan (rural) lebih tinggi dibandingkan areal perkotaan (urban). Penerimaan dosis untuk area pedesaan lebih tinggi dibandingkan dengan penerimaaan dosis area perkotaan. Dosis invidu efektif maksimum untuk area  pedesaan (rural)  adalah 9,24x10-2 Sv dan daerah perkotaan (urban) adalah 5,14x10-2 Sv. Risiko total terkena kanker untuk masyarakat yang berdomisili di area perkotaan lebih tinggi dibandingkan area pedesaan. Kata kunci: aktivitas, konsekuensi, dispersi, perkotaan, pedesaan ABSTRACTTHE ACTIVITIES AND RADIOACTIVE DISPERSION CONSEQUENCES FOR URBAN AND RURAL AREA. The consequences of radioactive releases of contaminants by humans is influenced by many factors such as the amount of activity that spread contaminants and environmental conditions. Environmental conditions include meteorological conditions, the contours of the site and contaminant pathways to humans. The purpose of this research is the analysis of the consequences of radionuclide activity and long half-life time due to accidents in urban and rural areas. The specific objective is to calculate the activity of the air dispersion and surface deposition, dose rate predictions and the risks posed to urban and rural areas as a function of the location. The estimates method used is simulation of the consequences on fission products dispersion in the atmosphere due to the postulated accident Beyond Design Basis Accident, BDBA. The calculation is performed for radioactive releases from accidents in 1000 MWe PWR simulated for rural and urban areas on Bojanegara-Serang site. Results of the analysis are that the activity of air dispersion and deposition surface at rural areas higher than urban areas. The Acceptance dose is higher for rural areas compared with urban areas. The maximum effective individual dose for rural areas is 9.24x10-2 Sv and urban areas is 5.14x10-2 Sv. The total risk of cancer for people who live in urban areas is higher than rural areas. Keywords: activity, consequence, dispersion, urban, rural 
ESTIMATION OF ROUTINE DISCHARGE OF RADIONUCLIDES ON POWER REACTOR EXPERIMENTAL RDE Pande Made Udiyani; Sri Kuntjoro
Urania: Jurnal Ilmiah Daur Bahan Bakar Nuklir Vol. 23 No. 1 (2017): Urania : Jurnal Ilmiah Daur Bahan Bakar Nuklir
Publisher : Badan Riset dan Inovasi Nasional

Show Abstract | Download Original | Original Source | Check in Google Scholar | DOI: 10.17146/urania.2017.23.1.3160

Abstract

Experimental power reactor (RDE), which is planned to be constructed by BATAN, is a kind of High Temperature Gas Cooled Reactor (HTGR) with 10 MWth power. HTGR is a helium gas-cooled reactor with TRISO-coated fuel that is able to confine fission products to be remained in the core. To ensure the safety for workers and public surroundings of the RDE site and to meet the regulatory body requirements for construction and operation, research is needed for environmental radiation in normal and abnormal condition. This study is focused on normal operating condition, while for the accident condition study will be carried out after the final design has been completed. Estimation of radiology in the environment involves the source term released into the environment under routine operation condition. The purpose of this study is to estimate the source terms released into the environment based on postulation of normal or routine operation of the RDE-10 MWth. The research approach starts with an assumption that there are defects and impurities in the TRISO fuel because of limitations during the fabrication. Mechanisms of fission products release from the fuel to the environment were created based on the safety features design of RDE. Radionuclides inventories in the reactor were calculated by the use of ORIGEN-2 whose library has been modified for HTGR type, while assumptions on TRISO fuel defects and release fraction for each compartment of the RDE safety systems are defined by a reference parameter. The results show that the important source terms of RDE are group of noble gases (Kr and Xe), halogen (I), Sr, Cs, H-3, and Ag. Activities of RDE source terms for routine operations have no significant difference with the HTR-10 source terms with the same power.
ANALISIS INVENTORI REAKTOR DAYA EKSPERIMENTAL JENIS REAKTOR GAS TEMPERATUR TINGGI Sri Kuntjoro; Pande Made Udiyani
Urania: Jurnal Ilmiah Daur Bahan Bakar Nuklir Vol. 22 No. 1 (2016): Urania : Jurnal Ilmiah Daur Bahan Bakar Nuklir
Publisher : Badan Riset dan Inovasi Nasional

Show Abstract | Download Original | Original Source | Check in Google Scholar | DOI: 10.17146/urania.2016.22.1.2745

Abstract

Relating to the plan of the National Nuclear Energy Agency (BATAN) to operate an experimental reactor of High Temperature Gas Reactors type (RGTT), it is necessary to reactor safety analysis, especially with regard to environmental issues. Analysis of the distribution of radionuclides from the reactor into the environment in normal or abnormal operating conditions starting with the estimated reactor inventory based on the type, power, and operation of the reactor. The purpose of research is to analyze inventory terrace for Experimental Power Reactor design (RDE) high temperature gas reactor type power 10 MWt, 20 MWt and 30 MWt. Analyses were performed using ORIGEN2 computer code with high temperatures cross-section library. Calculation begins with making modifications to some parameter of cross-section library based on the core average temperature of 570 °C and continued with calculations of reactor inventory due to RDE 10 MWt reactor power. The main parameters of the reactor 10 MWt RDE used in the calculation of the main parameters of the reactor similar to the HTR-10 reactor. After the reactor inventory 10 MWt RDE obtained, a comparison with the results of previous researchers. Based upon the suitability of the results, it make the design for the reactor RDE 20MWEt and 30 MWt to obtain the main parameters of the reactor in the form of the amount of fuel in the pebble bed reactor core, height and diameter of the terrace. Based on the main parameter or reactor obtained perform of calculation to get reactor inventory for RDE 20 MWT and 30 MWT with the same methods as the method of the RDE 10 MWt calculation. The results obtained are the largest inventory of reactor RDE 10 MWt, 20 MWt and 30 MWt sequentially are to Kr group are about 1,00E+15 Bq, 1,20E+16 Bq, 1,70E+16 Bq, for group I are 6,50E+16 Bq, 1,20E+17 Bq, 1,60E+17 Bq and for groups Cs are 2,20E+16 Bq, 2,40E+16 2,60E+16 Bq. Reactor inventory will then be used to calculate the reactor source term, and it will be used as the basis for calculating the distribution of radionuclides into the environment.
Co-Authors Jupiter Sitorus Pane Pande Made Udiyani