Jurnal Sains dan Teknologi Nuklir Indonesia
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THE VELOCITY MODEL IDENTIFICATION IN EARTHQUAKES PARAMETERS DETERMINATION IN THE NEAR REGIONAL OF THE BANGKA NPP CANDIDATE SITE
Full text linkCollecting information and earthquake investigation must be carried out to ensure the safety of the nuclear installation candidate site from seismic aspects. Accurate earthquake location data is essential for seismological studies. The accuracy must be improved from the velocity model factor in determining earthquake parameters in a limited number of stations and less azimuth coverage. The study aims to get the most appropriate velocity model for determining earthquake parameters in the near regional of the Bangka NPP candidate site. The study uses earthquake seismic data in Bangka seismic network with variations of the H-S, Crust 2.0, and TPI velocity models to determine earthquake parameters. The most appropriate velocity model is determined based on the comparison with BMKG results and the smallest errors in identifying earthquake parameters. The results show almost the same epicenter and origin time but different earthquake depths. The TPI velocity model best represents the velocity model in the near regional of the Bangka NPP candidate site. TPI falls into the criteria of tectonic earthquake type and most errors (latitude, longitude, and depth) in earthquake parameters determination are the smallest among other velocity models
STUDY OF PLUTONIUM UTILIZATION IN AP1000 REACTOR USE SRAC2006 AND JENDL 3.3 NUCLEAR DATA LIBRARY
Full text linkPreliminary Study of Plutonium Utilization in AP1000 Reactor Use SRAC 2006 and JENDL 3.3 has been conducted. Nuclear energy, especially for nuclear reactor, become important this day because the need of energy will increase along with the increasing of human population, the advanced technology and economic. The more nuclear reactor operated the more existence of plutonium stockpile. This study evaluated the standard of Westinghouse AP1000 reactor and ZrB2 as Integral Fuel Burnable Absorber (IFBA). Different fuel compositions of assembly type were analyze in by using SRAC 2006 code system with JENDL 3.3 nuclear data library. This study aiming to compare the neutronics characteristics of an UO2 and an (U,Pu)O2 assembly designs. Some results of the study show that optimal criticality of the fuel assembly can be accomplished by using 5% enrichment of U-235 for UO2 fuel and 9% plutonium fraction for (U,Pu)O2 fuel assembly
PERBANDINGAN DOSIS PERMUKAAN PADA PEMERIKSAAN THORAX ANAK MENGGUNAKAN METODE AUTOMATIC EXPOSURE CONTROL DAN METODE MANUAL
Full text linkPERBANDINGAN DOSIS RADIASI PADA PEMERIKSAAN THORAX ANAK MENGGUNAKAN METODE AUTOMATIC EXPOSURE CONTROL DAN METODE MANUAL. Automatic Exposure Control (AEC) pada pesawat sinar-X Digital Radiography (DR) secara otomatis dapat mengendalikan paparan radiasi, sehingga dapat menurunkan Dose Area Product (DAP) mencapai 61% tanpa mengurangi kualitas citra medis. Metode AEC dirancang untuk pasien dewasa, namun tidak menutup kemungkinan digunakan untuk pasien anak. Agar tingkat risiko kanker akibat radiasi pada anak dapat diminimalisasi, maka metode AEC ini menjadi penting untuk diaplikasikan. Dalam penelitian, dilakukan perbandingan metode AEC dan metode manual terhadap 60 pasien anak pemeriksaan thorax untuk memperoleh metode yang memberikan dosis permukaan lebih rendah. Pasien anak dikelompokkan dalam tiga kategori menurut usia, yaitu; 1-5 tahun, 6-10 tahun dan 11-15 tahun. Setiap kategori terdiri atas 10 pasien untuk metode AEC dan 10 pasien untuk metode manual. Pengukuran dosis permukaan menggunakan TLD LiF:Mg,Cu,P. Dari penelitian diperoleh dosis permukaan untuk Kategori-1 masing-masing 0,15±0,09 mSv untuk metode AEC dan 0,15±0,02 mSv untuk metode manual. Untuk Kategori-2 dan Kategori-3 masing-masing diperoleh 0,16±0,07 mSv (AEC), 0,21±0,06 mSv (manual) dan 0,15±0,04 mSv (AEC), 0,31±0,13 mSv (manual) secara berurutan. Metode AEC untuk pasien anak dapat meningkatkan keselamatan radiasi dan menekan kemungkinan risiko kanker
ELEMENTS CHARACTERIZATION IN RICE FLOUR AND FISH MEAL FOR LABORATORY COMPETENCY
Full text linkNowadays, nutrition problem becomes an important issue in many developing countries. Lack or excess macro and micro elements in food can interfere human health. Therefore, food safety needs a reliable analytical method in accuracy and precision. In this activity, characterization of toxic (As, Pb, Cd, Hg) and essential elements (Na, K, Ca, Mg, Fe,Cu, Zn) in rice flour and fish meal had been done using Neutron Activation Analysis (NAA) and Atomic Absorption Spectrophotometry (AAS). Both samples provided by The Asia Pacific Food Analysis Network (APFAN) on 2017. Three replications were prepared. Reducing the probability of contaminating the sample is a must. AAS needs homogenous liquid samples therefore samples were digested using microwave digestion to avoid loss of volatile elements from the samples. Evaluation on rice flour and fish meal samples analysis were based on Z-score value with 3 categories: satisfactory, questionable and unsatisfactory result. Both methods had satisfactory result in rice flour where Z-score value of K, Ca, Zn < 2 meanwhile AAS gave Mg, Fe, Cu, Cd < 2 in the same sample. NAA gave the Z-score 2 < Mg < 3 in rice flour. Satisfied performance in fish meal gave Z-score values of K, Ca, Mg, Fe, Zn < 2 for both of them. Values of Na < 2 and 2 < Hg < 3 obtained from NAA in fish meal and Z-score of As was < 2 with NAA. Moreover, 2 < Pb < 3 obtained from AAS in fish meal sample. These results showed that NAA and AAS are accurate and precise methods on food analysis in rice flour and fish meal from APFAN to maintain laboratory competency
OPPORTUNITY TO PRODUCE RADIOISOTOPES ASTATINE-211 USING DECY-13 CONCEPTUAL DESIGN WITH COMPUTATIONAL APPROACH
No full textTo catch up research gap with developed countries, Indonesia would build a cyclotron type accelerator that has the code name DECY-13. Detailed design and conceptual design of DECY-13 were published, thus to accelerated applied research of DECY-13, it is necessary to hold a preliminary study even before the cyclotron is commissioned. Astatine-211 (211At) is an alpha-rays emit radioisotope that is easy to direct labeling for targeted alpha therapy. Targeted alpha therapy (TAT) is the selectively deliver therapy that uses alpha-ray base radioisotopes that are produced using a cyclotron like DECY-13. DECY-13 was designed to accelerate a proton to 13 MeV. however, it does not rule out the possibility of accelerating alpha particles. A computational approach will be used to simulate the possibility of DECT-13 to accelerate alpha particles for the production of 211At from natural Bismuth. The theoretical calculation was predicting that the alpha particle (helium nucleus) could be accelerated in DECY-13, but the energy decreased increasingly after hitting niobium layer twice and helium cooling layer into 4.06 MeV. The 0.924 grams of natural bismuth was irradiated 8 hours long and 4 hours cooling. At EOB was not found radioisotopes, radioactivity and dose emitted. The inability to produce 211At because the energy of the accelerated alpha particles has not been able to penetrate the bismuth nucleus. the continuation simulation successfully predicts if the niobium layer thinned to 125 mm can be obtained 211At with low impurity. on the other side, if the energy of DECY-13 would be increased until 28 MeV 211At can be produced but the impurity was increased to. Furthermore, DECY-13 Cyclotron is not able to produce 211At from bismuth-209. To obtain 211At from 209Bi, it is necessary to create another engineering design of cyclotron or use another proton-base reaction
DESIGN OF SODIUM IODINE BASED SURVEYMETER WITH ATMEGA328P MICROCONTROLLER
No full textSurvey meter is a device for radiation exposure and dose rate measurements which is mainly used in radiation protection. The main purpose of this work is to present testing results of a designed surveymeter by comparing with a calibrated Peranuk surveymeter. The designed surveymeter consists of a NaI(Tl) scintillation detector as gamma radiation sensor with an ATMega328P processor as signal processing system and a 3.5-inch LCD as a data display. From the testing results, a count rate (cps) to dose rate (Sv/h) conversion factor of 0.0254 was obtained with dose rate reading deviations range from 0.03% to 6.26%
EFFECT OF GAMMA IRRADIATION ON GROWTH OF ESCHERICHIA COLI AND SALMONELLA SP.
Full text linkEscherichia coli was still detected in treated water and Salmonella sp. filled 90% of the pathogenic bacteria content in the Wastewater Treatment Plant (WWTP) sludge. This research aimed to know the effect of gamma irradiation on the growth of E. coli and Salmonella sp. Experimental bacteria were in the form of un-raw material, bacterial isolates. The experimental method of this research gave gamma irradiation doses 1, 2, 3, 4, and 5 kiloGray (kGy) to bacterial suspensions. The isolates were cultured on Nutrient Agar (NA) and followed by cultured on Nutrient Broth (NB) to get the suspensions. The suspensions were put in microtubes for irradiation then followed by enumeration on Plate Count Agar (PCA) in Total Plate Count (TPC) based on SNI-2897-2008. This research proved that the higher dose of gamma irradiation had been given, the lower growth of bacteria (or were the higher death number of bacteria) resulted. Decimal Reduction Dose (D10) value of E. coli and Salmonella sp. were 0,3 kGy and 0,35 kGy, and totally dead by ≥ 3 kGy and ≥ 4 kGy. For further research might be conducted on raw material such as WWTP sludge, wastewater, drinking water, river water, soil water, or organic fertilizer.EFFECT OF GAMMA IRRADIATION ON GROWTH OF ESCHERICHIA COLI AND SALMONELLA SP
COMPUTATION STUDY OF RADIOISOTOPES GALLIUM-68 (68Ga) PRODUCTION USING LONG-LIVED & HIGH ACTIVITY METHODS
Full text linkRadioisotopes used for gamma-ray-based diagnostics have the main problem that imaging resolution quality.Gallium-68 is a positron (β+) emitting radioisotope that has better imaging resolution than gamma-based radioisotopes. Gallium-68 (68Ga) can be produced by irradiating natural gallium or zinc-68 enriched as a target with protons in an accelerator facility. Indonesia has planned to build a cyclotron type accelerator that operates in 13 MeV proton energy and 50 µA proton beam who has initials named DECY-13. Before it was commissioned for radioisotopes production purpose that was must conduct a preliminary study to determine 68Ga optimum irradiation time and properties, one of which was the monte carlo computation method using PHITS v3.24 software. Simulations were begun by irradiating proton with natural gallium target for 25 days with 2 days cooling and zinc-68 enriched for 120 minutes with cooling 10 minutes. The results at EOB of the long-lived process using the natGa target obtained total radioactivity of 189.42 MBq (5.12 mCi). The total radioactivity result of high activity process which used 68Zn enriched as a target was 268.6 GBq (7.259 Ci). the radioactivity was compared with another accelerator, that the long-lived process was too small and uneconomical to done, but the high activity process was feasible to produce. The results of this research expected will be considered as a feasibility study for the 68Ga production process in Indonesia in the future
Performance of 113Sn/113mIn Generator Prototype based on Zirconium Oxide for Radiotracer Applications in Industry
Full text linkThis paper describes the results of the research of 113Sn/113m radioisotope generator at the Centre for Applied Nuclear Science and Technology - National Nuclear Energy Agency with the aim of making radioisotope generator for radiotracer applications in industry. This research discussed the need of short half-life radiotracer for several material phases such as oil, water, gas and solid. Based on desired physical properties of half life, radiation type and energy, 113mIn radioisotope was selected. Thus, the performance of 113Sn/113mIn generator prototype based on zirconium oxide was determined for this purpose. The final product specification in the form of 113mInCl3 is clear solution, pH 2 with obtained yield of 95 %, radionuclide purity of 95 % and radiochemical purity of 95 %
ANALYSIS OF CS-137 RADIONUCLIDE ON THE EAST JAKARTA FLOOD CANAL WATER SAMPLES USING GAMMA SPECTROMETER
Full text linkRadionuclide Cs-137 is a radioactive element that is soluble in water, so its distribution in the environment is influenced by mixing and diffusion, so that Cs-137 radionuclide can cause harmful effects on biotic and abiotic components in the waters. The East Jakarta Flood Canal is a macro drainage system for the city of DKI Jakarta that drains water to Marunda beach, most of the water quality has been polluted with light to heavy levels of pollution. This study aims to determine the water quality of the East Jakarta Flood Canal including in situ and ex situ physical and chemical properties parameters (temperature, pH, salinity and TDS) and Cs-137 radionuclide concentration parameters and the distribution pattern of Cs-137 radionuclides at each sampling point. The samples used were water and kale, the samples were filtered and concentrated from the initial volume of 20 liter of water to 1 liter of water and 10 kilograms to 1 kilogram of Kale plant. The levels of Cs-137 were measured with a gamma spectrometer instrument for 3600 seconds, then data analysis was carried out. The results obtained are the concentration level of Cs-137 in Simplo KBT water ranging from 0-1.571 Bq/L, for duplo 0-0.424 Bq/L while for kale plant 0-3,228 Bq/Kg the overall results are within the quality standard limits set by regulations. the head of BAPETEN Number 7 of 2013 concerning the limit value of environmental radioactivity, which is 2.6×102 Bq/L