bluuebunny/crossref_metadata_2025_split huggingface dataset:
Analysis of external radiation exposure from building materials using resrad-build (case study: perumnas bumi guwosari)
Authors: Anggraeni Diana Fitria , Wijaya Gede Sutresna , Muharini Anung 
Published: February 2020

Abstract
One of the natural radiation that is not realized by humans comes from radionuclides in building materials. So, it becomes necessary to study the natural radioactivity in various building materials to calculate the annual effective dose of the public in Perumnas Bumi Guwosari room model. In this paper, activity concentration of 226Ra, 232Th and 40K in 5 cement, 5 sand, 5 red brick, and 5 ceramic samples were bought directly from the local hardware store in Yogyakarta were determined by gamma-ray spectrometry with HPGe detector. The activity concentration of 226Ra, 232Th and 40K ranged from 23.87 ± 20.88 to 49.31 ± 31.04 Bq.kg−1, 11.56 ± 12.41 to 36.62 ± 14.34 Bq.kg−1 and 0.1443 ± 11.2029 to 58.82 ± 15.01 Bq.kg−1, respectively in various samples. The radium equivalent activity ranged from 17.7338 to 136.8901 Bq.kg−1 are lower than the limit of 370 Bq.kg−1 set by UNSCEAR. The highest value of external and internal hazard indices was found in ceramic samples 0.3705 and 0.5317 are below the UNSCEAR recommendation (Hext ⩽ 1 and Hin ⩽ 1). The results of calculating the annual effective dose using RESRAD-BUILD ranged 0.654-0.661 mSv.y−1 is lower than the annual recommended limit of 1 mSv.y−1. The parameters that most influence the increase in external radiation dose rate from building materials are the composition, density, and thickness of the floor and wall.
Design of Irradiation Facilities at Grid E-1 of Plate Type Research Reactor Bandung
Authors: Bahrum E S , Wibowo H , Setiadi Y , Handiaga W , Basuki P , Maulana A , Febrian M B 
Published: February 2020

Abstract

Design of Irradiation Facilities at Grid E-1 of Plate Type Research Reactor Bandung. Plate Type Research Reactor Bandung (PTRRB) core design is one of the result of PTRRB research programs. In the previous study the irradiation facilities at grid E-1 has not been designed and also distribution of thermal, epithermal and fast neutron flux at grid E-1 has not been studied. Since that data is very important especially in radioisotope production and neutron beam tube analysis, therefore in this study irradiation facilities at grid E-1will be designed. Previous PTRRB core design is a base for designing irradiation facilities at grid E-1. Considering geometrical of grid E-1 and aluminum tube dimension there are three possibilities aluminum tube configuration. The configurations are configuration 1, 2 and 3. Each configuration was modelled as arrangement of four aluminum tubes and each tube filled by four aluminum irradiation capsules. That configuration was starting point to made MCNP PTRRB reactor core model so there are three MCNP PTRRB reactor core model. MCNP PTRRB reactor core model is needed because MCNP software are computer program for calculating excess reactivity and neutron flux distribution at grid E-1. Result excess reactivity calculation of three configuration indicate that after installing irradiation tube excess reactivity is lower than of limit excess reactivity value 10.9 % of neutronic safety criteria of PTRRB design. Based on neutronic safety criteria, the three configuration is accepted for irradiation facilities PTRRB. Neutron flux calculation result of three configuration reveals that the highest neutron flux is located at capsule no II and III. Profile of thermal neutron flux, epithermal neutron flux and fast neutron flux of three configurations are similar. Neutron flux of thermal, epithermal and fast neutron of three configuration are slightly different. The calculation result reveal that highest thermal neutron flux at grid E-1 is 2.70 × 1013(n/cm
2.sec) at configuration 2. Based on neutronic safety criteria and thermal neutron flux, configuration 2 is appropriate for irradiation facilities of PTRRB.
Determination of micro essential element Fe in foodstuffs using instrumental neutron activation analysis (INAA)
Authors: Yusuf Saeful , Suprapti Siti , Istanto  , Mulyaningsih Rina , Sutisna  , Alfian  
Published: February 2020

Abstract
Fe is an essential macro element that humans need to carry out their physiological processes. Although many factors that cause stunting cases in Indonesia, Fe anemia in pregnant women, breastfeeding women and infants under two years is believed to be one of the causes of stunting. This study will determine the content of Fe in 73 types of local food from Mamuju Regency, West Sulawesi Province. The information can be useful in preventing stunting, especially stunting caused by iron deficiency. The Fe element is determined using a neutron activation analysis technique that utilizes the G.A. Siwabessy Multipurpose Reactor. The sample irradiation was carried out at a rabbit system that has a thermal neutron flux of about 3.1013 n.cm−2.sec−1. Data acquisition of gamma-ray emitted from target irradiated was performed using gamma-ray spectrometry coupled to the high-resolution detector. Fe concentration in foodstuffs was calculated using the NAA-comparative method. The results showed that green vegetables such as kangkung (Ipomoea Aquatica Forsk), bayam (amaranthus spp), kemangi (ocimum citriodorum), daun pakis (diplazium esculentum), daun katuk (sauropus androgynous), daun seledri (Apium graveolens), daun singkong (cassava leaves), cesim (brassica rapa) and buncis (phaseolus vulgaris) have an elemental content of Fe > 100 mg/kg. Kangkung, bayam, and kemangi are green vegetables that are rich in the element Fe, the concentration of Fe in the vegetables more than 280 mg/kg. Concentrations of Fe minerals in vegetables are higher compared to Fe minerals in beef or other protein sources. The green vegetables are suitable foodstuff to overcome Fe anemia in pregnant women, breastfeeding women and infants under two years.
Design of reflector TRIGA mark II Bandung waste container shielding using micro shield 7.02.
Authors: Irsyad  , Purnomo Sigit , Oetami Rini Heroe 
Published: February 2020

Abstract
Reflector TRIGA Mark II Bandung waste container shielding using Microshield 7.02 has been conducted. In 1996, TRIGA Mark II power was upgraded from 1MWt into 2MWt, and the reflector was one part of the reactor core that was changed. Reflector waste consists of graphite with activated Co-60. In 2015 the activity was 0.557 Ci with 1,221.5 Kg weight. This large radioactive waste needs to be removed from Bandung Nuclear Area into PTLR-Serpong Nuclear Area. This removal process needs calculations and the basic design of the waste container. Pure lead material is planned to be used for attaining requirements standards of radioactive container category base on Transport Index score. In addition, MicroShield 7.02 is a software that is used for helping to analyze shield thickness and could count exposure rate out of the waste container. This software was also used in this research to calculate the lead thickness and demonstrate the radioactivity in several points. The result of simulation with this software is; lead thickness for the container is 3 cm; the container category is III-Yellow with; Transport Index score is 189 or bigger than 10. With tubular shape with 3 cm thickness it will use 1,945.13 kg pure lead. Then, the dose rate on the surface of the container is 128.6 mSv/hr.
Growth of TiN thin film on Al 5083 deposited using dc sputtering technique for improving their hardness and corrosion resistance
Authors: Ananda Gifari M , W Andriyanti , Haerul Ahmadi , M Rasyidi Ichsan 
Published: February 2020

Abstract
Aluminium 5083 is an Al-Mg alloy commonly used in ship hull construction. Although it has good corrosion resistance, this aluminium alloy is susceptible to corrosion in extreme environments for a long time. This research aims is to improve the ability of aluminium 5083 deposited by TiN to increase hardness and corrosion resistance using dc sputtering process. This research was carried out with several processes, namely the study of literature, preparation of tools and materials, manufacturing of test objects, coating process, characterization, data analysis, and report making. Hardness testing was done by Vickers method, corrosion testing was carried out by electrochemical method, and crystal structure test using diffraction X-ray. The results of this study were sputtering time 120 minutes increasing hardness 81.6% or becoming 94.7 VHN. The best corrosion rate at 90 minutes sputtering time is 0.0001 mpy. The formation of the TiN phase in the direction of 111, 200, and 202 planes respectively, was shown through peaks at 2-theta at 36.68°, 42.72° and 61.98°.
Labeled of Irradiated Chitosan with IODIUM-131 Radioisotope
Authors: Widyasari Eva Maria , Sriyani Maula Eka , Sugiharti Rizky Juwita , Daruwati Isti , Abbas Basril , Pangerteni Dewi Sekar , Darwis Darmawan 
Published: February 2020

Abstract
Chitosan is a polysaccharide from the deacetylation process of chitin, a compound derived from crustacean animal exoskeletons. Chitosan has benefits in various fields, one of them is in health field. Chitosan is known to be able to bind with fat so that it can reduce cholesterol levels in the blood, besides chitosan also has activities as an antibacterial and anticancer. Irradiated chitosan is carried out to degrade chitosan to smaller molecular weight and is easily absorbed to the body. As a new drug, many stages of testing are carried out to determine the mechanism and effectiveness of chitosan compound specifically as an anticancer compound. One of the required data is preclinical study data using animal model. Nuclear techniques offers the results of preclinical study that can identify quickly and accurately the distribution of a drug in the body with the radiotracer principle. Therefore it is necessary to make T-chitosan labeled compounds irradiation (131I-chitosan-75kGy) and compared with 131I-chitosan labeled compounds non-radiation (131I-chitosan) as controls. In this study, the optimum formulation of chitosan and chitosan-75kGy with radioisotope iodine-131 with radiochemical purity > 90% was obtained. Chitosan can be labeled by iodine-131 with the formulation of 150 μL (0.5%) chitosan, 20 μl (5 mg / mL) chloramine T, 20 μl (10 mg / mL) sodium metabisulphite, 10 μL Nal3I and 5 minutes incubation time at room temperature. While the optimum formulation of chitosan-75kGy labeled is 100 μL (0.5%) chitosan-75kGy, 10 μl (5 mg / mL) chloramine T, 10 μl (10 mg / mL) sodium metabisulphite, 10 μL Na131I with 1 minute incubation time at room temperature. Radiochemical purity testing was carried out using ascending paper chromatography method with whatman 1 paper as a stationary phase. To separate impurities in the form of I2, chloroform is used as the mobile phase, whereas methanol 90% is used to separate impurities in the form of I−. With this successful in producing labeled chitosan, it is expected that the effectiveness of irradiated chitosan as anticancer compounds can be identified.
Steady-state Thermal-hydraulic Analysis of the TRIGA 2000 Reactor Core when Using Configuration of 105 Fuels
Authors: Nazar Reinaldy , Pane Jupiter Sitorus 
Published: February 2020

Abstract
The continuity of the TRIGA 2000 reactor operation is determined by the fuel temperature and the primary cooling water temperature. Currently operating the TRIGA 2000 reactor using 105 fuel configurations it is difficult to reach 1000 kW of power, because the fuel temperature and primary coolant temperature in the core are high. It causes boiling and bubble formation in the reactor core, thus reducing neutron moderation in the core. The results of neutronic calculations on the configuration of 105 fuels in the core at this time, it is known that heat generation is focused into the center of the core, and some fuels have large power fluxes, so that some of these fuels produce high cladding surface temperatures as well and cause boiling. In this research, thermal hydraulic analysis has been carried out using the CFD program package for the configuration of 105 fuels in the core. Based on the results of research on the reactor operated at 500 kW power, the hottest channel is at B5 fuel with the power it generates of 9.43 kW, the maximum surface temperature of the fuel cladding is 126.41 °C, and the temperature of coolant wets 119.92 °C. This temperature has exceeded the saturation temperature of the reactor cooling water 112.4 °C, so that sub-cooled boiling is possible. This situation is in accordance with the conditions that occur in the operation of the TRIGA 2000 reactor, where at 500 kW power has begun to observe bubbles coming out of the reactor core. One effort that can be done to reduce the temperature of the TRIGA 2000 reactor core is to do reshuffling and increase the amount of fuel used.
Physico-chemical characterization of the terbium-161 radioisotope through separation based on cartridge LN resin column from irradiated of enriched Gd2O3 target
Authors: Aziz A 
Published: February 2020

Abstract
According to WHO, cancer is the second leading cause of death in the world and the seventh cause of death in Indonesia. Currently, cancer sufferers are increasing every year and become a national problem in health. Terbium-161 (161Tb) is a low β−-emitter of radiolanthanide (Eβ
- an average of 0.150 MeV and t1/2
for 6.9 days) that is potential for cancer therapy as an alternative to 177Lu which has been widely used in nuclear medicine. Physico-chemical characterization of 161Tb radioisotope in the form of 161TbCl3 final product solution has been studied including radiochemical purity, radionuclide purity, clarity, acidity (pH), and its stability. Irradiation of the Gd2O3 enriched target (98.4% 160Gd isotope enrichment) was carried out at Bandung TRIGA 2000 reactor for ± 3 days. The separation of 161Tb radionuclide from the Gd/Tb matrix has been done by the extraction chromatography method using two pieces of LN (Eichrom) resin cartridge column. The radiochemical purity of the final product of 161TbCl3 radioisotope solution was determined using paper chromatography and paper electrophoresis methods. Radionuclide purity of fractions resulted from separation as well as the final products of radioisotope 161TbCl3 was determined through analysis using a γ-ray spectrometer equipped with a multichannel analyzer (MCA) and HP-Ge detector. The clarity of the solution was determined visually, while the determination of acidity (pH) was carried out using the universal pH indicator paper. In this study, the final product of 161TbCl3 solution has Physico-chemical characteristics that meet the requirements for nuclear medicine application, namely clear, has a pH of ∼ 1, radiochemical purity of 99.31 ± 0.62%, and radionuclide purity of 99.96 ± 0.03%. The stability of radionuclide purity still meets the requirements (> 99%) for 2 weeks after preparing the final product, but 161TbCl3 solution with radiochemical purity more than 95% was stable until 3 weeks at room temperature.
Analysis of coolant flow distribution to the reactor core of modified TRIGA Bandung with plate-type fuel
Authors: Wardhani V I S , Pane J S , Dibyo S 
Published: February 2020

Abstract
A conversion of the TRIGA reactor Bandung has been planned by replacing fuel from rod type to plate type. The fuel replacement causes the fuel arrangement or reactor core configuration should be changed as well as the cooling system. Currently, the reactor cooling system takes place by natural convection with the flow direction from the bottom to the top of the core. The replacement of plate-type fuel with a small distance between plates causes the core cooling process to decrease, therefore to make more effective the forced convection cooling system with the direction of upward flow is required. It is expected that the cooling process will increase. The ability of the cooling system depends on flow distribution in the core at the time of reactor in operating, therefore it is necessary to analyze the distribution of coolant flow and the velocity distribution of the cooling system from the top reactor pool to the reactor core to determine that the coolant flow from the inlet pipe mostly goes to the core. The purpose of this research is to analyze the distribution of coolant flow and flow velocity to the reactor core. The analysis was carried out in a simulation using computational fluid dynamics FLUENT software by creating reactor core modeling. The result shows that the cooling water flows from above along the reactor pool, then the stored energy is reduced so that the flowing slowdown. In this case, resulting in evenly flow distribution to the reactor core.
Multiband Electromagnetic Wave Absorption Study on Nanocrystalline (1-x)NiFe2O4/(x)BaTiO3 Composites
Authors: Sukirman E. , Sarwanto Y. , Ahda S. , Taryana Y. , Purwanto S. 
Published: February 2020

Abstract
Multiband electromagnetic wave absorption have been studied on nanocrystalline (1-x) NiFe2O4 (NFO)/(x)BaTiO3 (BTO) composites. The samples were synthesized by solid state reaction using high energy milling (HEM) instrument. The composite samples were characterized using X-ray Diffractometer (XRD) and vibrating sample magnetometer (VSM) instrument. The X-ray diffraction (XRD) patterns of all the samples show single phase and free from impurities. The NFO sample can be indexed to a single cubic crystal structure with a space group of Fd-3m, No. 227. While, the BTO sample can be indexed to a single tetragonal crystal structure with a space group of P4mm, No. 99. The composite samples consist of two phases, namely NFO and BTO showing soft magnetic performance. The mass magnetization is in the range of 20.0–49.0 emu/g. The electromagnetic parameters of the composites were measured by a vector network analyser in the frequency range of 2 GHz to 18 GHz. The results indicated that (1-x) NiFe2O4 / (x) BaTiO3 composites display three-band electromagnetic wave absorption. The 0.5NiFe2O4 / 0.5BaTiO3 composite displays three-band reflection loss which is larger than the other one and the three-band reflection loss are almost the same, i.e., below the -15 dB. From these experiments it can be concluded that the 0.5NiFe2O4 / 0.5BaTiO3 composite is good candidate for electro-magnetic wave absorption.
X-ray diffraction (XRD) profile analysis of pure ECAP-annealing Nickel samples
Authors: Prasetya Ahadi Damar , Rifai Muhammad , Mujamilah  , Miyamoto Hiroyuki 
Published: February 2020

Abstract
X-Ray Diffraction (XRD) profile of pure equal channel angular pressing (ECAP)-annealing nickel samples has been thoroughly investigated for studying the material structures changes that imply to the mechanical behavior. Nickel-based material can be used for several applications such as biomaterial, gear, and some part of the instrument at nuclear facilities, which require high-grade standard material properties. ECAP is one kind of severe plastic deformation (SPD) techniques to obtain excellent mechanical properties without adding another element. However, the ECAP process generates metastable structures due to some mismatch structure and inhomogeneous stress within the material. This problem can usually be resolved by annealing after the ECAP process. In this article, pure Nickel was processed by ECAP at 423 K for two passes. The post-ECAP annealed will be carried out at the temperature range from 298 K until 1373 K. The microhardness test results indicate that the ECAP process increases the microhardness significantly, which remains stable after annealing until 773 K. At higher annealing temperature, the mechanical properties will drop suddenly and reach the microhardness value of pure pre-ECAP Nickel. This behavior could be explained clearly by the XRD data analysis result, which shows similar behavior structure changes. XRD data initially show peak shifting to lower 2θ value, which indicates an expansion to a higher lattice parameter, then at the higher annealing temperature, the diffraction peaks split gradually. This peak splitting could be indexed as pure pre-ECAP Ni peaks, which could be related to the drop of the microhardness value.
Somatic embryogenesis on irradiated callus of garlic (Allium Sativum L.)
Authors: Maryono Marina Yuniawati 
Published: February 2020

Abstract
The research was done at the Tissue Culture Laboratory of Center for Application of Isotope and Radiation Technology, Jakarta. Callus derived from shoot tip of garlic cloves was exposed to gamma rays, then cut into sized of 1 mm3 and cultured in Gamborg medium enriched with plant growth regulators (PGRs) depends on the treatment. The PGRs applied are. The experiment was arranged in a randomized factorial design with 2 factors and 3 replications. The first factor was the doses of gamma rays (0, 10 and 20 Gy) and the second factor was different concentrations of PGRs (untreated, 1 and 2 ppm of thidiazuron (TDZ) and Zeatin). The result indicated that the application of 2 ppm TDZ or Zeatin promoted development on irradiated callus at the dose 10 Gy. The highest number of the shoot and the longest shoot were obtained from non-irradiated callus grown on medium enriched with 2 ppm TDZ, followed by 1 and 2 ppm Zeatin, 1 ppm TDZ and without PGRs. Irradiated callus at the dose 10 Gy grown on medium with 2 ppm TDZ was able to form a shoot, while other irradiated callusat the dose 29 Gy were not able to form the shoot.
Visualization of dose distribution inside soft X-ray machine based on OSL technology
Authors: Nagara Nanda 
Published: February 2020

Abstract
In this study, as a part of the development of the radiation mapping technology, we are planning to develop the gamma-ray imager based on a passive detector such as a dosimeter. For this purpose, we demonstrated the use of nanoDot OSLD as a passive detector being irradiated inside a soft x-ray machine then combined the irradiation position (qualitatively) with radiation dose (quantitatively) for visualization purpose. The experimental results showed that the NanoDots exhibit good linearity and reproducibility when subjected to soft X-rays machine, Hence, the nanoDots showed a promising potential for visualization of dose distribution.
Characterization ionic species fine particulate samples in Indonesia by ion chromatography
Authors: Kusmartini Indah , Adventini Natalia , Kurniawati Syukria , Lestiani Diah Dwiana , Damastuti Endah , Sari Dyah Kumala 
Published: February 2020

Abstract
Particulate is one indicator of air pollutants derivative from a complex mixture of large and small particles that are decomposed. Particulate diameter at 2.5 to 100 mm consists of dust originating from agriculture, building construction, and vehicles. Particulates with a diameter of less than 2.5 mm are generally made from fossil fuels and vehicle exhaust containing various specific chemicals or ions. In this activity, characterization of chemical content and specific ions in fine particulates was carried out in fine air particulate samples by ion chromatography. Sampling was carried out in several regions in Indonesia such as Pekanbaru, PalangkaRaya, Manado, Ambon, Jayapura, Denpasar, and Surabaya. The validation methods using reference materials. On the other hand, verification of measurements is carried out regularly with ED-XRF therefore accurate and precise quality can be obtained. The results of this activity obtained several cations and anions such as Ca2+, K+, Mg2+, Na+, SO4
2-, NO3
−, F−, and Cl−. The results obtained from this activity are expected to be used as basic data and scientific-based references for regional/national in formulating, taking appropriate and directed actions and policies to solve the problem of air pollution.