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INDONESIA
Jurnal Sains dan Teknologi Nuklir Indonesia (Indonesian Journal of Nuclear Science and Technology)
Published by Badan Tenaga Nuklir Nasional
ISSN : 14113481     EISSN : 25031287     DOI : https://search.crossref.org/?q=%22jurnal+sains+dan
Core Subject : Health, Science, Social, Engineering,
Biochemistry, Genetics & Molecular Biology Energy Environmental Science Materials Science & Nanotechnology Mechanical Engineering Medicine & Pharmacology Physics
Focus of Publication in Indonesian Journal of Nuclear Science and Technology : Result of experiment in the field of nuclear science and technology and its applications in various fields. Acceptable topics include: Radioisotope, Radiopharmacy, Nuclear Medicine, Nuclear Radiation and its Measurement, Nuclear Physics and Reactors, Nuclear Instrumentation and Radioactive Waste including its applications in the fields of health, biology, industry, agriculture, metallurgy and environment
Arjuna Subject : Kimia(semua kategori) - Kimia (Lain-Lain)
Articles 280 Documents
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Performance of 113Sn/113mIn Generator Prototype based on Zirconium Oxide for Radiotracer Applications in Industry Duyeh Setiawan; Ade Suherman; Titin Sri Mulyati
Jurnal Sains dan Teknologi Nuklir Indonesia (Indonesian Journal of Nuclear Science and Technology) Vol 22, No 1 (2021): February 2021
Publisher : BATAN

Show Abstract | Download Original | Original Source | Check in Google Scholar | DOI: 10.17146/jstni.2021.22.1.6486

Abstract

This 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 %.
COMPUTATION STUDY OF RADIOISOTOPES GALLIUM-68 (68Ga) PRODUCTION USING LONG-LIVED & HIGH ACTIVITY METHODS Badra Sanditya Rattyananda; Muhamad Abdulkadir Martoprawiro; Aminatus Arifah; Aristia Pratiwi Meliawati; Merika Indri Widayanti; Rasito tursinah; Yanuar Setiadi
Jurnal Sains dan Teknologi Nuklir Indonesia (Indonesian Journal of Nuclear Science and Technology) Vol 22, No 2 (2021): Agustus 2021
Publisher : HIMNI

Show Abstract | Download Original | Original Source | Check in Google Scholar | DOI: 10.17146/jstni.2021.22.2.6440

Abstract

Radioisotopes 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.
EFFECT OF GAMMA IRRADIATION ON GROWTH OF ESCHERICHIA COLI AND SALMONELLA SP. Dita Aisyiyah Larasati; Bambang Suharto; Ruslan Wirosoedarmo; Irawan Sugoro
Jurnal Sains dan Teknologi Nuklir Indonesia (Indonesian Journal of Nuclear Science and Technology) Vol 22, No 2 (2021): Agustus 2021
Publisher : HIMNI

Show Abstract | Download Original | Original Source | Check in Google Scholar | DOI: 10.17146/jstni.2021.22.2.6018

Abstract

Escherichia 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.
THE STRATIFICATION BEHAVIOR OF REACTOR MATERIALS IN THE FRAMEWORK OF MOVING PARTICLE SEMI-IMPLICIT Yacobus Yulianto; Asril Pramutadi Andi Mustari; Amir Baliana
Jurnal Sains dan Teknologi Nuklir Indonesia (Indonesian Journal of Nuclear Science and Technology) Vol 22, No 2 (2021): Agustus 2021
Publisher : HIMNI

Show Abstract | Download Original | Original Source | Check in Google Scholar | DOI: 10.17146/jstni.2021.22.2.6314

Abstract

In reactor research, the safety of the reactor plays an important role. Besides the experiment research, computational simulation can also provide important information about the behavior of materials inside the reactor core. The Moving Particle Semi-Implicit (MPS) method assists in providing information about the reactor material computationally. In this study, the stratification process of several materials, i.e. the melts of PbBi, PbLi, and Pb in combination with Al, have been investigated by simulation. The time to achieve stratified conditions for each material has been obtained where each paired material needs 0.5 seconds to reach the stratified condition. It is also obtained that the Pb-Al is the fastest in reaching the stratified condition among the other used materials.
ANALYSIS OF CS-137 RADIONUCLIDE ON THE EAST JAKARTA FLOOD CANAL WATER SAMPLES USING GAMMA SPECTROMETER Indah Dwi Cahyati; Hendrawati Hendrawati; Ghulam Fathul Amri
Jurnal Sains dan Teknologi Nuklir Indonesia (Indonesian Journal of Nuclear Science and Technology) Vol 22, No 2 (2021): Agustus 2021
Publisher : HIMNI

Show Abstract | Download Original | Original Source | Check in Google Scholar | DOI: 10.17146/jstni.2021.22.2.6438

Abstract

Radionuclide 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.
OPPORTUNITY TO PRODUCE RADIOISOTOPES ASTATINE-211 USING DECY-13 CONCEPTUAL DESIGN WITH COMPUTATIONAL APPROACH Badra Sanditya Rattyananda; Duyeh Setiawan; Ade Suherman; Muhamad Basit Febrian; Yanuar Setiadi; Laila Roikhatul Jannah
Jurnal Sains dan Teknologi Nuklir Indonesia (Indonesian Journal of Nuclear Science and Technology) Vol 23, No 1 (2022): February 2022
Publisher : HIMNI

Show Abstract | Download Original | Original Source | Check in Google Scholar | DOI: 10.17146/jstni.2022.23.1.6713

Abstract

To 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 Santiko Tri Sulaksono; Rony Djokorayono
Jurnal Sains dan Teknologi Nuklir Indonesia (Indonesian Journal of Nuclear Science and Technology) Vol 23, No 1 (2022): February 2022
Publisher : HIMNI

Show Abstract | Download Original | Original Source | Check in Google Scholar | DOI: 10.17146/jstni.2022.23.1.6683

Abstract

Survey 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%.
ANALYSIS ON HEAT LOSS IN WATER HEATING TANK BASED ON TEMPERATURE SETTING VARIATION DURING NATURAL CIRCULATION FLOW USING FASSIP-02 TEST LOOP Mulya Juarsa, S.Si., MESc.; Andrea Shevaladze Al Amin
Jurnal Sains dan Teknologi Nuklir Indonesia (Indonesian Journal of Nuclear Science and Technology) Vol 23, No 1 (2022): February 2022
Publisher : HIMNI

Show Abstract | Download Original | Original Source | Check in Google Scholar | DOI: 10.17146/jstni.2022.23.1.6542

Abstract

Based on the nuclear reactor accident in Fukushima due to an earthquake that caused a tsunami that turned off the electrical system for the cooling water pump. So that the reactor core melts due to the failure of the active cooling system, based on this incident, a passive cooling system that does not require external energy for emergency cooling is needed to prevent such an accident. Experimental research on the passive cooling system based on natural circulation flow to improve reactor thermal management performance during an accident has been done using the FASSIP-02 Test. One of the important components of the simulation of heat sources in nuclear power plants is the water heating tank (WHT). This study aimed to obtain the analysis results of heat absorption in water in WHT and the value of heat loss. The research method was carried out by calculating changes in the internal energy of water in WHT and heat loss for variations in water temperature settings from temperatures of 40 oC, 50 oC, and 60 oC in WHT at steady-state conditions for 5 hours experiment. The results showed that the entire surface of the tank resulted in heat losses of 10.85 kW, 9.2 kW, and 8.37 kW, which occurred at temperature settings of 40 oC, 50 oC, and 60 oC as a whole.
THE ANALYSIS OF LAPSE RATE PROFILE IN THE SITE CANDIDATE OF NUCLEAR POWER PLANT (NPP) AT GOSONG BEACH, BENGKAYANG REGENCY– WEST KALIMANTAN Deni Septiadi; Agung Hari Saputra; Rista Hernandi Virgianto; Arif Yuniarto; Muhammad Elifant Yuggotomo
Jurnal Sains dan Teknologi Nuklir Indonesia (Indonesian Journal of Nuclear Science and Technology) Vol 23, No 1 (2022): February 2022
Publisher : HIMNI

Show Abstract | Download Original | Original Source | Check in Google Scholar | DOI: 10.17146/jstni.2022.23.1.6578

Abstract

The lapse rate profile in the site candidate for the Nuclear Power Plant (NPP) at Gosong Beach Bengkayang, has been investigated to obtain a description of the lability of the atmosphere and upper air as part of a meteorological aspect safety study in the plan to develop a NPP site. The study of the lapse rate was carried out using air data on the reanalysis of the Global Data Assimilation System (GDAS) by extracting air temperature data at each altitude level so as to obtain a lapse rate of up to 25 km. Daily data was processed during 2021 and transformed in the monthly average profile data to describe the lapse rate profile in January – December 2021. Tropopause was identified with average altitude about 16.6 km and stratosphere at 20.5 km with a lapse rate about -0.21 ℃/100 m. The surface layer to 200 m have lapse rate from 0.7 ℃/100 m - 0.9 ℃/100 m at 00.00 Universal Time Coordinated (UTC) and 0.5 ℃/100 m -0.6 ℃/100 m at 12.00 UTC
ANALYSIS OF EYE LENS EFFECTIVE DOSE OF WORKERS DURING CARDIAC CATHERIZATION EXAMINATION IN A CATHLAB ROOM Samsun Samsun; Eka Putra Syarif H; Sriyatun Sriyatun; Gando Sari; Guntur Winarno; Ary Sasongko
Jurnal Sains dan Teknologi Nuklir Indonesia (Indonesian Journal of Nuclear Science and Technology) Vol 23, No 1 (2022): February 2022
Publisher : HIMNI

Show Abstract | Download Original | Original Source | Check in Google Scholar | DOI: 10.17146/jstni.2022.23.1.6753

Abstract

In the current era, many radiological imaging technologies are used, one of which is the C-Arm equipment technology, which is capable of imaging three-dimensional patient objects in real time using fluoroscopy techniques. This study aims to obtain and evaluate the effective radiation dose received around the eye organs of radiation workers during cardiac catheterization. The main tool uses the C-Arm modality, and the TLD detector chip. The object of observation is the area around the eye organs of radiation workers consisting of one doctor and one nurse. Catheterization was carried out on 10 patients with different examination times. Research results: in the area around the eyes without protective glasses; the effective dose received by doctors' eyes ranges from 0.0011 to 0.0054 mSv, while for nurses it ranges from 0.0010 mSv to 0.0025 mSv. It was found that the effective dose received around the eye organs was lower than the dose value set by Perka Bapeten No. 8 of 2011 which is 20 mSv and ICRP 203 which is 500 mSv per year.

Page 26 of 28 | Total Record : 280

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