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INDONESIA
Jurnal Forum Nuklir
Published by Badan Tenaga Nuklir Nasional
ISSN : -     EISSN : -     DOI : -
Core Subject : Science,
Materials Science & Nanotechnology
Jurnal Forum Nuklir (JFN) adalah jurnal ilmiah bertaraf nasional dengan ruang lingkup semua aspek yang terkait dengan ilmu pengetahuan nuklir, teknologi nuklir, termasuk pendidikan dan sumber daya manusia nuklir. JFN (ISSN 1978-8738) diterbitkan oleh Sekolah Tinggi Teknologi Nuklir BATAN
Arjuna Subject : -
Articles 208 Documents
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DISTRIBUSI FLUKS NEUTRON TERMAL DAYA 2 MW PADA POSISI IRADIASI B-6, D-9 DAN G-7 REAKTOR RSG-GAS Jaka Iman; Asnul S.; Kawkab M.; Royadi Royadi
Jurnal Forum Nuklir JFN Vol 8 No 2 November 2014
Publisher : BATAN

Show Abstract | Download Original | Original Source | Check in Google Scholar | Full PDF (716.087 KB) | DOI: 10.17146/jfn.2014.8.2.3706

Abstract

DISTRIBUSI FLUKS NEUTRON TERMAL DAYA 2 MW PADA POSISI IRADIASI B-6, D-9 DAN G-7 REAKTOR RSG-GAS. Distribusi fluks neutron termal telah dilakukan pada tiga posisi iradiasi (B-6, D-9 dan G-7) teras 83 reaktor RSG GAS. Pengukuran dilakukan dengan metode aktivasi keping emas. lradiasi keping dilakukan pada daya menengah dengan mengoperasikan sistem pendingin primer. Aktivitas keping diukur dan dihitung pada saat keluar dari reaktor. Distribusi fluks neutron termal dapat dihitung dari aktivitas keping yang terukur tersebut. Dari hasil analisis diperoleh fluks neutron termal di posisi B-6 pada daya 2 MW, posisi ditengah sebesar 9,70.10+13 n/cm2.s., fluks neutron termal di posisi iradiasi D-9, pada posisi ditengah sebesar 9,79.10+13 n/cm2.s. Fluks neutron termal di posisi iradiasi G-7 pada posisi ditengah 9,81.10+13 n/cm2.s. Dengan pengukuran ini diperoleh data fluks neutron termal terkini untuk mendukung produksi radioisotop, pengembangan elemen bakar dan komponen reaktor, penelitian dalam bidang sains materi dan berbagai litbang lain dalam bidang industri nuklir.Kata kunci: distribusi fluks neutron termal, posisi iradiasi, RSG-GAS
NUCLEAR ENERGY IS THE ANSWER TO COPE WITH THE LACK OF ENERGY AND GLOBAL WARMING Wisnu Arya Wardhana
Jurnal Forum Nuklir JFN Vol 3 No 1 Mei 2009
Publisher : BATAN

Show Abstract | Download Original | Original Source | Check in Google Scholar | Full PDF (109.584 KB) | DOI: 10.17146/jfn.2009.3.1.3294

Abstract

NUCLEAR ENERGY IS THE ANSWER TO COPE WITH THE LACK OF ENERGY AND GLOBAL WARMING. This paper of nuclear energy is the answer to cope with the lack of energy and global warming based on the analysis of energy demand which is increasing rapidly, meanwhile the energy reserve is limited and decreased. Mostly world’s energy is generated by fossil fuel energy, mainly oil and coal. Fossil fuel energy and industrial activities produce green house gases (GHG) such as : COx, CH4, N2O, and CFC which cause of global warming. Global warming gives bad impact to environment and to human being. Every country in the world needs  sufficient  energy,  but  the  energy resources  is limited  and  decreased.  The answer for this solution must be an energy source which doesn’t produce green house gases. Why nuclear energy is chosen to cope with the lack of energy and global warming will be explained briefly in this paper.
PENGUKURAN KUALITAS BERKAS CITRA RADIOGRAFI NEUTRON PASCA PENAMBAHAN SISTEM TOMOGRAFIDIFASILITAS RN1 BATAN-SERPONG Juliyani Juliyani; Setiawan Setiawan; Fahrurrozi A.; Sutiarso Sutiarso
Jurnal Forum Nuklir JFN Vol 6 No 2 November 2012
Publisher : BATAN

Show Abstract | Download Original | Original Source | Check in Google Scholar | DOI: 10.17146/jfn.2012.6.2.3447

Abstract

PENGUKURAN KUALITAS BERKAS CITRA RADIOGRAFI NEUTRON PASCA PENAMBAHAN SISTEM TOMOGRAFI DI RN1 BATAN SERPONG. Pengukuran kuatitas berkas citra radiografi neutron pasca penambahan sistem tomografi di RN1 BATAN Serpong, telah dilakukan. Pengukuran bertujuan untuk menentukan kualitas berkas neutron berdasarkan standar ASTM E-545-05. Pengukuran dilakukan dengan metode langsung (film radiografi) menggunakan cuplikan standar Sensitivity Indicator (SI) dan Beam Purity Indicator (BPI), serta film AGFA D3. Kualitas berkas neutron yang keluar dari tabung berkas ditentukan oleh karakteristik kolimator yang digunakan. Pada saat film radiografi neutron dioperasikan bersamaan dengan sistem tomografi, kualitas berkas yang didapat secara kuantitatif dari hasil pengukuran densitas citra dari cuplikan BPI menggunakan densitometer, mendapat jumlah neutron termal: 40,20 %; neutron terhambur: 0,70 %; gamma: 1,50 %; produksi pasangan: 3,30 %; jumlah garis dan yang terlihat masing-masing: 6 dan 4. Sedangkan apabila film radiografi neutron saja yang dioperasikan, mendapatkan jumlah neutron termal: 62,20 %; neutron terhambur: 0,50 %; gamma: 1,80 %; produksi pasangan: 2,30 %; jumlah garis dan yang terlihat masing-masing: 7 dan 4. Kualitas citra radiografi neutron pada saat film radiografi dioperasikan bersamaan dengan sistem tomografi, tidak baik (buram). Kualitas citra radiografi neutron apabila film radiografi neutron saja yang dioperasikan menjadi lebih baik (terang dan kontras), berdasarkan standar ASTM E-545-05 diklasifikasikan ke dalam kategori II. Dapat disimputkan bahwa untuk mendapatkan kualitas citra radiografi neutron yang lebih baik, maka film radiografi tidak dioperasikan bersamaan dengan sistem tomografi.
ANALISIS AKUMULASI RADIOFARMAKA TC-99M MDP PADA PASIEN KANKER PAYUDARA Dian Milvita; Sri Mulyadi D.T. Basa; Hajjatun Khairah; Fadil Nazir
Jurnal Forum Nuklir JFN Vol 8 No 1 Mei 2014
Publisher : BATAN

Show Abstract | Download Original | Original Source | Check in Google Scholar | Full PDF (1758.461 KB) | DOI: 10.17146/jfn.2014.8.1.3481

Abstract

ANALISIS AKUMULASI RADIOFARMAKA Tc99m MDP PADA PASIEN KANKER PAYUDARA. Telah dilakukan analisis akumulasi radiasi dari Tc99m MDP pada pasien kanker payudara. Pada penelitian ini digunakan teknik ROI (Region of Interest), kamera gamma dan dose calibrator. Data diambil dari 32 pasien kanker payudara, 63 % diantaranya sudah bermetastasis dan 37% lainnya tidak bermetastasis, kemudian data tersebut diolah) untuk melihat rerata dan trend (pola) dari akumulasi radiasi Tc99m MDP. Hasil analisis menunjukkan bahwa rerata akumulasi radiofarmaka Tc99m MDP di jantung, sternum, spine, sacrum, sacroiliact joint kiri dan sacroiliact joint kanan masih cukup tinggi. Pasien dengan akumulasi tertinggi pada organ tertentu merupakan pasien yang kankernya sudah bermetastasis dan letak metastasis kanker sesuai dengan organ tersebut, hal ini menggambarkan bahwa tulang yang sudah terkena kanker akan menyerap zat radiofarmaka lebih banyak dibandingkan tulang sehat. 
CONCEPTUAL DESIGN OF CONTROL ROD DRIVE MOTOR TYPE MAGNETIC JACK FOR NUCLEAR POWER PLANT Fahmi Alfa Muslimu
Jurnal Forum Nuklir JURNAL FORUM NUKLIR VOL 15 NO 1 MEI 2021
Publisher : BATAN

Show Abstract | Download Original | Original Source | Check in Google Scholar | DOI: 10.17146/jfn.2021.15.1.6340

Abstract

The Control Rod Drive Motor (CRDM) controls the reactor power of a G.A Siwabessy and automatically shuts it down during an emergency using a three-phase motor that drives a ball-nut spindle attached to the magnetic SCRAM through the transmission gear. However, there are several weaknesses associated with this design, such as the inability of the ball nut to rotate when a disturbance occurs at the motor limit switch continuously. This causes the threads on the control rod shaft to wear out due to friction and release from the holder. Therefore, this research aims to develop a CRDM with a magnetic jack for a nuclear plant, which moves the extension shaft and the control rod components vertically and linearly. The control rod's motor must pull, insert, hold, or drop it from any point. This conceptual design is the first step in determining prototyping design criteria with a magnetic jack to understand the working mechanism. The control rod gripping motion simulation was also presented using ANSYS Rigid Dynamics to reduce the failure at the design phase before prototyping. The simulation results showed no collision on each component capable of affecting the overall system performance. Therefore, the control rod motor functions properly in carrying out the pulling and lowering movements on 19.1 mm infrequency.
REVIEW: APPLICATION OF IRRADIATION TECHNOLOGY IN NATURAL RUBBER VULCANIZATION PROCESS Andri Saputra, S.ST., M.Eng.
Jurnal Forum Nuklir JURNAL FORUM NUKLIR VOL 15 NO 1 MEI 2021
Publisher : BATAN

Show Abstract | Download Original | Original Source | Check in Google Scholar | DOI: 10.17146/jfn.2020.14.3.6253

Abstract

APPLICATION OF IRRADIATION TECHNOLOGY IN NATURAL RUBBER VULCANIZATION PROCESS. A new vulcanization technology is needed in order to eliminate some potential negative impacts of conventional vulcanization such as contain nitrosamines and allergen proteins that are harmful to health, toxic residues of accelerator compound, cannot be done at room temperature, and sulfur crosslinking contribute to acidification impact. One of the advanced technologies that can be used in the processing of polymers, such as natural rubber, is irradiation using gamma rays. This study is descriptive analysis by conducting a literature search from books and journals of national and international reputation. Radiation in latex of natural rubber will cause free radical formation, crosslinking, and chain scission between polyisoprene chains, and also produce mostly H2 gas. For crosslinking, materials with G(S):G(X) ratios <1.00 are preferred. The dose increase till certain dose led to an increase in the cross-link density of the irradiated rubbers, while apparently, the degradation mechanism has occurred for doses greater than optimum doses. The tensile strength at break of radiation vulcanizate has long been presumed to be lower than that of sulfur vulcanizate or peroxide vulcanizate. The approaches for enhancing radiation crosslinking could be defined by incorporation with filler, increasing the possibility of polymer radical recombination, and increasing the amount of polymer radicals.
BIOETHANOL PRODUCTION FROM COCONUT HUSK USING THE WET GAMMA IRADIATION METHOD Putra Oktavianto; Risdiyana Setiawan; Ilhami Ariyanti; Muhammad Fadhil Jamil
Jurnal Forum Nuklir JURNAL FORUM NUKLIR VOL 14 NO 2 NOVEMBER 2020
Publisher : BATAN

Show Abstract | Download Original | Original Source | Check in Google Scholar | DOI: 10.17146/jfn.2020.14.2.5908

Abstract

BIOETHANOL PRODUCTION FROM COCONUT HUSK USING the WET GAMMA IRRADIATION METHOD. The use of coconut husk has only been used as a material for making handicrafts such as ropes, brooms, mats, and others or just burned. The combustion of coconut husk can cause air pollution. In fact, coconut husk can be used as a raw material for bioethanol production so that the beneficial value of coconut husk will also increase. One way of bioethanol production from coconut husk is by irradiating the coconut husk. The coconut husk irradiation technique to be carried out in this study is the wet irradiation technique. Wet irradiation is carried out to accelerate the process of bioethanol production because at the time of irradiation, cellulose has been hydrolyzed and glucose has been formed so that it is more efficient in time and use of the material so that the cellulose hydrolysis process is not necessary. The coconut husk samples were wet because they were mixed with 4% NaOH and were irradiated using a gamma irradiator from STTN-BATAN Yogyakarta with a dose of 30 kGy and 50 kGy and 0 kGy (or without irradiation). Then the sample is fermented with the fungus Saccharomyces Cerevisiae from tape yeast to form ethanol. Ethanol is purified and then analyzed for concentrations using pycnometric and refractometric methods. The result is that the highest ethanol content is without irradiation (0 kGy), this is due to the low dosage used. However, the main point in this wet method research is evidence of hydrolysis of cellulose by the formation of gluoxane after irradiated wet coconut husk, and with Fehling A and B analysis, brown deposits are seen proving that glucose has been formed.
Intercomparison of Gamma Cell 220 Irradiator Facilities and Dr. Mirzan T Razzak Gamma Irradiators Using Harwell Dosimeters Bimo Saputro
Jurnal Forum Nuklir JURNAL FORUM NUKLIR VOL 15 NO 1 MEI 2021
Publisher : BATAN

Show Abstract | Download Original | Original Source | Check in Google Scholar | DOI: 10.17146/jfn.2021.15.1.6284

Abstract

The gamma irradiator is a multi-purpose facility that possibly used to preserve food, sterilize medical equipment, and conduct genetic engineering and polymerization processes, during which the absorbed dose of the product is critical. The standardization of product quality assurance was regulated by the IAEA Technical Document Number 409 considering Dosimetry for Food Irradiation and ISO 14470 and 11137-3 on Food Irradiation, as well as the Guidance on Dosimetric Aspects of Development, Validation, and Routine Control, respectively. The absorbed dose was influenced by the movement of the product to the source, its position, the amount of radioactive activity in the facility, and the dose rate in the irradiation room. The dosimeter performance test and quality assurance of the system were conducted using the Facility Intercomparison Technique which tested the dosimeter (measuring instrument) at 2 different facilities to determine the performance of the measuring instrument.. In this study, 2 irradiation facilities were tested using a Harwell routine dosimeter in the dose range of 1 kGy to 30 kGy and  20 dose points. The results showed that the highest deviation reached 19% and 21% at the Gamma Cell 220 and the Dr. Mirzan T Razzak Gamma irradiator facilities. This elevated the performance of the dosimeters to determine the precision accuracy of the dose-measuring instrument.
SAFETY ASSESSMENTS FOR SUPPORTING THE APPLICATION OF NUCLEAR TECHNOLOGY IN INDONESIA AND A COMPREHENSIVE STUDY ON HIGH NATURAL RADIOACTIVITY AREA Abarrul Ikram; Ismanto Jumadi; Nurokhim Nurokhim; Eka Djatnika Nugraha
Jurnal Forum Nuklir JURNAL FORUM NUKLIR VOL 14 NO 2 NOVEMBER 2020
Publisher : BATAN

Show Abstract | Download Original | Original Source | Check in Google Scholar | DOI: 10.17146/jfn.2020.14.2.6408

Abstract

SAFETY ASSESSMENTS FOR SUPPORTING THE APPLICATION OF NUCLEAR TECHNOLOGY IN INDONESIA AND A COMPREHENSIVE STUDY ON HIGH NATURAL RADIOACTIVITY AREA. Historically BATAN was established to investigate the negative impacts of nuclear explosions previously conducted in the Pacific area. However, this governmental institute is presently tasked to carry out research and development as well as services in the field of radiation safety and metrology. Therefore, this study aim to determine the activities carried out by BATAN in assessing the safety of workers and the environment. For instance, a standard source of dosimetry laboratory (SSDL) is used in calibration services to successfully support radiotherapy, with the highest achievement in the Designated Institute (DI) for Ionizing Radiation. The health research covers the application of gamma rays to create malaria vaccine, diagnose metabolic diseases with nuclear medicine techniques, and microdosimetry through radiodiagnostic assessment. This study also determined the effective dose and epidemiological study of radioecology and radiation biology in Mamuju (HBRA), which provides a unique opportunity to examine the health effects of chronic low-level radiation exposure to humans. Furthermore, the authors collaborated with Hirosaki University to obtain valuable information on the essential need to assess the health and physical status as well as cytogenetic and deoxynucleotide acid (DNA) damages in the lymphocytes of local populations. Dosimetry study was conducted by direct measurement in the field area by analyzing external radiation exposure of indoor and outdoor gamma dose rate. The internal radiation assessment was conducted by taking urine and inhaled air (radon) from the residents. Studies through the cytogenetic response supported by γ-H2AX, G0, and G2 micronucleus assays and TP53 showed no impacts on the natural radiation with significant differences compared to the control. Marine radioecology studies and radionuclides monitoring throughout the Indonesian archipelago showed no negative impacts as well. Nuclear emergency practice needs to be routinely conducted in the Center for strengthening safety and security cultures.
The Implementation of Planning and Budgeting Redesign System in National Nuclear Energy Agency Nata Wijaya
Jurnal Forum Nuklir JURNAL FORUM NUKLIR VOL 15 NO 1 MEI 2021
Publisher : BATAN

Show Abstract | Download Original | Original Source | Check in Google Scholar | DOI: 10.17146/jfn.2021.15.1.6475

Abstract

BATAN is presently applying the RSS concept of planning and budgeting redesign systems to prepare a work plan and budget document for 2021. This concept changes the nomenclature of programs, activities, and outputs that are input into the KRISNA. It also influences the substance of programs, activities, and outputs of each budget. The implementation of the RSPP concept is expected to strengthen the money follow program concept for the successful implementation of programs and activities in accordance with statutory regulations

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