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All Journal International Journal of Natural Science and Engineering Computational and Experimental Research in Materials and Renewable Energy (CERiMRE) Journal of Engineering and Technological Sciences
Seno, Haryo
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Aerospace Engineering Automotive Engineering Chemical Engineering, Chemistry & Bioengineering Civil Engineering, Building, Construction & Architecture Computer Science & IT Electrical & Electronics Engineering Energy Engineering Materials Science & Nanotechnology Physics

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Environmental Radioactivity Concentrations and Assessment of Radiological Hazards in Soil Around Bandung Nuclear Area Chussetijowati, Juni; Seno, Haryo; Muliawan, Dani
Computational And Experimental Research In Materials And Renewable Energy Vol 5 No 2 (2022): November
Publisher : Physics Department, Faculty of Mathematics and Natural Sciences, University of Jember

Show Abstract | Download Original | Original Source | Check in Google Scholar | DOI: 10.19184/cerimre.v5i2.31989

Abstract

Bandung nuclear area is an area which is nuclear reactor named TRIGA 2000 and research laboratory located. The reactor and research laboratory are utilized for training, researching and radioisotopes production that has potential to contaminate the environment. Environmental radioactivity monitoring is done periodically to find out potential radioactive release from activities inside Bandung nuclear area to surroundings. However, the assessment of radiological hazards to determine the potential radiological dangers to humans and environment around Bandung nuclear area is not done yet. The objective of this study is assessing the radiological hazards in Bandung nuclear area by comparing the data from soil samples taken in environment radiological monitoring activity with the recommendation data based on UNSCEAR and other references to find out the radiological hazards that potentially affect to humans, where this assessment has never been carried out in this area. The assessment of radiological hazards in this study is limited to Ra-226, Th-232 and K-40 nuclides because contributing to radiation dose received by human. The study was conducted by collecting soil samples from several sampling points inside and outside Bandung nuclear area. Then, the nuclides of Ra-226, Th-232 and K-40 contained in soil samples are measured by using the gamma-ray spectrometry method with high resolution detector that is HPGe (High Purity Germanium) and a computer-based Multichannel Analyzer (MCA). The results indicated that the concentration of environmental radioactivity ranged between 11.02 to 32.66 Bq/kg for Ra-226; 19.44 to 43.83 Bq/kg for Th-232 and 56.00 to 183.39 Bq/kg for K-40. This study also obtained results that the radiological hazard of the gamma dose rate ranged from 23.54 to 40.23 nGy/h, the radium equivalent was 51.77 to 89.78 Bq/kg; the external hazard index was 0.14 to 0.24 and the internal from 0.18 to 0.33; the index of radioactivity level was 0.37 to 0.63. The annual effective dose equivalent for outdoor ranged from 0.03 to 0.05 mSv/y and indoor was 0.12 to 0.20 mSv/y. The lifetime cancer risk for outdoors ranged from 0.10x10–3 to 0.17x10–3 and indoor was 0.4x10–3 to 0.69x10–3. The values of radiological hazard were below the international requirements. There is no potential risk of natural radiation of gamma ionizing radiation exposure in soil samples around the Bandung nuclear area for workers, the public, and the environment.Keywords: Environment, Radiological, Hazard, Gamma, Spectrometry.
Performance Analysis of Radiation Detection Devices in Elevated Natural Radiation Zones: A Case Study of Mamuju Regency, West Sulawesi Indonesia Abdullah, Adi Rahmansyah Amir; Permana, Sidik; Srigutomo, Wahyu; Maulana, Alan; Seno, Haryo; Purnama, Dikdik Sidik; Tursinah, Rasito; Humolungo, Ismail; Zulfahmi, Zulfahmi
Journal of Engineering and Technological Sciences Vol. 57 No. 1 (2025): February
Publisher : Directorate for Research and Community Services, Institut Teknologi Bandung

Show Abstract | Download Original | Original Source | Check in Google Scholar | DOI: 10.5614/j.eng.technol.sci.2025.57.1.8

Abstract

Three radiation detection tools were employed to assess natural radiation levels in Mamuju Regency, West Sulawesi, Indonesia. These tools comprised the NaI(Tl) Scintillator, the Geiger Muller Counter (GMC), and the Electronic Personal Dosimeter (EPD). The NaI(Tl) Scintillator and GMC measured ambient dose equivalent (H*(10)), while the EPD exclusively gauged personal dose equivalent (Hp(10)). A total of 75 measuring points were designated for assessment. Results from H*(10) measurements indicated that the GMC recorded an average H*(10) 41% higher than that of the NaI(Tl) Scintillator, with specific rates of 0.769 µSv/h and 0.457 µSv/h, respectively. Both instruments exhibited proficiency in detecting elevated levels of radiation. Discrepancies in the outcomes were attributed to differences in detector type and efficiency. The GMC, equipped with an energy-compensated detector, demonstrated enhanced efficiency compared to the NaI(Tl) Scintillator, particularly when subjected to high energy flux radiation. Anomalies emerged in the Hp(10) measurements, which surpassed the H*(10) measurements. This difference is due to the EPD's use of a conventional GM detector, which is capable of detecting gamma, beta, and X-ray radiation
Gamma Spectroscopy Prototype Design to Identify Radioactive Elements Djokorayono, Rony; Sulaksono, Santiko Tri; Seno, Haryo; Utomo; Saptowati, Hasriyasti; Santoso, Puji; Hermana, Ferly; Wiranto BS; Sumaryanto, Agus
International Journal of Natural Science and Engineering Vol. 7 No. 2 (2023): Juli
Publisher : Lembaga Penelitian dan Pengabdian kepada Masyarakat

Show Abstract | Download Original | Original Source | Check in Google Scholar | DOI: 10.23887/ijnse.v7i2.65908

Abstract

The identification system for radioactive elements used the single-channel analyzer (SCA) gamma spectroscopy method. However, the process of producing the spectrum was still quite long because it had to go through the process manually by scanning its energy; one of the other radioactive elements is gamma spectroscopy. This research aims to develop a prototype gamma spectroscopy that allows the identification of radioactive elements. In this study, researchers used an experimental method by designing a gamma spectroscopy prototype consisting of a 2.5 cm diameter NaI(TL) detector equipped with a photomultiplier, high voltage module, preamp module, pulse shaping module, sample hold module, and Atmega microcontroller with an LCD display resolution of 128 × 64. The results of testing this prototype were carried out with various radioactive samples. Researchers managed to identify radioactive elements by measuring electrical pulses produced by NaI(TL) detectors. Background counting, which is the result of enumeration from detectors without radioactive material, was identified and eliminated. The distribution pattern has a random nature, the energy resolution of the spectroscopy consists of 1024 channels, and the counting time can be set as needed via the reset button. The main finding of the study was that the gamma spectroscopy prototype was able to provide a clear picture of the energy spectrum of nuclear radiation, allowing good identification of radioactive elements. The results of this study have important implications in the field of identification of radioactive elements and can be used in a variety of scientific and industrial applications involving nuclear radiation.
Co-Authors Abdullah, Adi Rahmansyah Amir Alan Maulana Chussetijowati, Juni Hasriyasti Saptowati Hermana, Ferly Humolungo, Ismail Muliawan, Dani Puji Santoso Purnama, Dikdik Sidik Rasito Tursinah, Rasito Rony Djokorayono Sidik, Adi Permana Sulaksono, Santiko Tri Sumaryanto, Agus Utomo Wahyu Srigutomo Wiranto BS Zulfahmi Zulfahmi