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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 5 Documents
 1 
Search results for , issue "Vol 23, No 1 (2022): February 2022" : 5 Documents clear
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.

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