bluuebunny/crossref_metadata_2025_split huggingface dataset:
Ambient dose measurement from high natural background radiation (HNBR) in Botteng Utara Village, Mamuju-Indonesia
Authors: Shilfa S N , Jumpeno B Y E B , Nurokhim  , Kusdiana  
Published: February 2020

Abstract
The terrestrial environment is one of the contributors to natural background radiation. Mamuju Regency, located in the Province of West Sulawesi Indonesia is known as the high natural background radiation (HNBR) area due to its high terrestrial exposure. Botteng Utara Village is one of the areas with dose rates up to 5 mSv/y in Mamuju district. For this reason, measurements were taken to determine the ambient dose received by society. In situ measurements were carried out in Botteng Utara Village using 70 OSL (Type EX-OSLD Environment) installed in 70 houses. The selection of houses is made with various types of building materials, randomly selected from 10 hamlets with each of 7 houses per sub-village. Measurements were done for ± two months from February 20, 2019 to April 12, 2019. The range of ambient dose achieved by measurement was from 51 up to 176 mRem/h. Further investigation using a larger sample number and longer time should be performed to validate this study’s results. This result will serve as a baseline for further research regarding the possibility of radiation effects on the society in Botteng Utara Village in Mamuju district.
The assessment of mitotic and nuclear division indexes as biomarkers for estimating the risk on the health of residents exposed to the high natural radiation of Mamuju, West Sulawesi
Authors: Purnami Sofiati , Lubis Masneli , Suryadi  , Syaifudin Mukh 
Published: February 2020

Abstract
Cell proliferation is a potential biomarker and closely associated with the assessment of general cytotoxicity of chemical and physical agents under study. However, the utilization of these biomarkers in response to environmental stimuli such as natural radiation has not been adequately explored. This research aimed to assess the mitotic index (MI) and nuclear division index (NDI) in lymphocytes as biomarkers for predicting the risks on the health of residents living in high natural radiation area (HNRA) in Salletto and Ahu villages of Mamuju as a studied group. As a control group, people living in another region of Topoyo village were also studied. The observation of these both parameters was done according to the standard protocol as described by the International Atomic Energy Agency (IAEA). The result showed that the percentage of MI of lymphocytes obtained from the studied area was lower compared to those of the control area (6.48 vs. 9.41) whereas the percentage of NDI of lymphocytes obtained from the studied area was higher compared to those of control area (1.59 vs. 1.32). This finding is similar to previous studies in an adjacent area. The NDI obtained from manual counting was much lower than that obtained from the automatic machine for counting (1.59 vs. 22.46), of which it is due mainly to a factor in criteria for counting the cells. MI for the female is lower than that of male and there is a trend of decreasing mitotic index with increasing age in the same group. It is concluded that natural radiation exposure did not affect the proliferation of cells of local people which suggests a low risk of radiation-exposed related to inflammation.
Self-diffusion coefficient of fe, pb, ni and Cr by molecular dynamics simulation using the potential morse
Authors: Ma’nun Luq’il , Arkundato Artoto , Misto  , Purwandari Endhah , Sujito  
Published: February 2020

Abstract
The molecular dynamics simulation using the Morse potential has been applied to calculate the value of self-diffusion coefficients D(T) of some pure metals as Pb, Cr, Ni, and Fe. The simulation then was done using the MOLDY molecular dynamics program. The procedure to calculate these coefficients following several steps: first, determining the Morse potential parameters as

D

, a and r
0; second, simulating the material under consideration using Moldy based on the appropriate ensemble; third, diffusion coefficient calculation using the Green-Kubo method for specific temperature; and fourth, the temperature-dependent diffusion coefficient D(T) based on the Arrhenius. The simulation work has obtained the best results as following: for Pb metal the Morse potential parameter (a = 1.4795 A−1, r
0 = 3.733 Å, and

D
=
0.2348

eV

) with

D

(
T
)

=
9.68
×

10

−
9

exp

(

−
3890.79

R
T

)

[

m
2

/
s

]

; for Cr metal the potential parameters (

D
=
0.3292

eV

, a = 1.1005 A−1, and r
0 = 2.2032 Å), with

D

(
T
)

=
1.73
×

10

−
3

exp

(

−
8725.54

R
T

)

[

m
2

/
s

]

; for Ni metal the Morse potential parameter (

D
=
0.3784

eV

, a = 1.0649 A−1, r
0 = 2.085 Å), with

D

(
T
)

=
8.5
×

10

−
4

exp

(

−
15794.9

R
T

)

[

m
2

/
s

]

; and for Fe metal the potential parameter (

D
=
0.4174

eV

, a = 1.5974 A−1, r
0 = 2.840 Å) with

D

(
T
)

=
4.22
×

10

−
7

exp

(

−
5878.49

R
T

)

[

m
2

/
s

]

. The calculated diffusion coefficients of the work have significant application as for the corrosion study of steels in nuclear reactor design.
Influence of blankets bore pile on soil characteristics irradiator gamma merah putih of serpong
Authors: Saptowati Hasriyasti , Wahono Tri , Praptana  , Bagas Andrew 
Published: February 2020

Abstract
in determining the planning of a building foundation there are two things that must be considered in the bottom soil of the foundation, namely the carrying capacity of the permitted soil and the magnitude of the foundation decline. Both of these factors determine the stability of building construction. The stress due to the existence of the building above must be able to be carried by the soil layer under the foundation and must be safe from collapse. In general, the use of pile foundation is used if the subgrade under the building does not have enough bearing capacity to carry the weight of the building and the load above it, and also if the location of the hard ground has sufficient carrying capacity to carry the weight of the building above in a very deep position. At the location of the irradiator it is known from the results of soil testing obtained hard soil at a depth of 30 m so that pile drilling is carried out to that depth. When bore pile casting is carried out it turns out that the required volume of concrete exceeds the planned volume based on BQ (bill of Quantity), so we do the pile wrapping to prevent the mix concrete from flowing out. From the results of several method changes and packaging materials, the results show that the most effective two-layer geotextile wrapper reduces concrete wastage (which functions to carry forward the burden of the building structure above it from the surface of the ground to the layer of hard soil underneath).
Elemental Analysis of Wepal Sample Using INAA In The Framework of The 2017 IAEA Proficiency Test Program
Authors: Sutisna  , Alfian  , Istanto  
Published: February 2020

Abstract
The 2017 IAEA Proficiency Test Program has been carried out to improve the performance of the Neutron Activation Analysis (NAA) laboratory. This activity has been organized by the International Atomic Energy Agency (IAEA) cooperated with Wageningen Evaluating programs for Analytical Laboratory (Wepal). Eight samples of ISE (soil samples) and IPE (plant samples) obtained from Wepal under the 2017 Proficiency Test program. Moisture content has been determined using a gravimetric method at 105-110 C and 100-105 for ISE and IPE samples respectively. Target irradiation was carried out for long, medium, and short irradiation using a thermal neutron flux of about 2.3x1013 n.cm−2.s−1 at the rabbit facility of GA Siwabessy reactor. Elemental analysis has been done using kay zero (k0) and comparative method of Instrumental Neutron Activation Analysis (INAA). On the kay zero-INAA method, the Al-0.1%Au alloy of IRMM-530R has been used as a flux monitor. Short half-life radionuclide was calculated using an Excel program for the comparative method and correction for a dead and counting time was applied. Quantitative determination has been carried out on a dry weight basis. The water content of the IPE sample was higher than that of the ISE sample. The result of the moister content of the IPE sample was in the range of 8% to 10%; meanwhile the moister content of the ISE sample was 2% to 6%. The elements detected on the IPE samples were less than that on the ISE sample. The elements of Na, Mn, V, Cl, Sc, Fe, Co, Zn, As, Br, Rb, Zr, Sb, Cs, Ba, La, Ce, U, and Th have been determined on ISE sample. In the meantime, for IPE sample, the elements of K, Na, Mn, Cl, Mg, Al, Ca, Cr, Fe, Co, Zn, Br, Rb, Sr, Sb, Cs, La, and Th can be evaluated quantitatively. Most of the elements evaluated have Z-score and Zeta-score of-3 to +3, which indicate good analytical performance for some elements, but for the element, some of them are out layer.
Optimization of the extraction process in the synthesis of high specific activity Molybdenum-99 by Szilard Chalmers reaction
Authors: Febrian Muhamad Basit , Fadhillah Firdha Nur , Agma Muldjadji 
Published: February 2020

Abstract
Molybdenum-99 (99Mo) is a parent radioisotope of technetium-99m (99mTc) which is widely used as diagnostic radiopharmaceutical because of its short half-life and ideal gamma-ray energy of 140 keV. Separation of 99mTc and 99Mo is mainly carried out using a radioisotope generator of 99Mo / 99mTc. Alumina column inside the generator has a low absorbency capacity of Mo (20 mg Mo / g alumina). Low alumina capacity requires 99Mo with high specific activity in order to minimize the amount of alumina so that the generator size could be kept as small and simple. High specific activity 99Mo alternatively can be obtained by Szilard Chalmers’s reaction in irradiated molybdenum phthalocyanine (MoPc) target material. The purpose of this study was to optimize the extraction condition of 99Mo from irradiated MoPc. The study was conducted with stages consisting of the determination of the number of solvents, the effect of extraction time, and Physico-chemical characterization of 99Mo solution. 5-gram MoPc was irradiated in TRIGA Reactor Bandung for 3 days with 5.1012 n.s−1.cm−2 neutron flux. Extraction optimization was carried out using THF, DMSO and NaOH 3M solvents with a ratio of solvent : MoPc (v(ml):w(mg)) were 1: 5, 1:10, 1:25, 1:50, and 1:75. Extraction time was varied for 1, 2, 3, 4, and 5 hours. 3M NaOH with a volume ratio of 1: 5 with an extraction time of 1 hour was considered as an optimum condition to extract 99Mo from MoPc. This condition produced an extraction yield of 54.21% and an enrichment factor of 322.53 times with 95% radiochemical purity as (99MoO4)2-.
Design of the controller module of mobile carrier radioactive source
Authors: Atmoko D F , Triyanto J , Amin H D M , Harahap F , Jayadiharja T 
Published: February 2020

Abstract
A control module for mobile carrier radioactive source has been designed. Mobile carrier radioactive source is a tool used to carry out testing for radiation characteristics both statically and dynamically and to conduct calibration on the Radiation Portal Monitor according to the requirements of SNI IEC 62244-2016. The control module is designed to meet the that requirements, it can set a carrier speed of at least 8 km/h, it can adjust the height of the radioactive source between 1 m and 2.5 m, it has automatic forward and backward direction mode. Furthermore, the mobile carrier can be controlled remotely for personnel tester safety. The control module can stop the mobile carrier suddenly when an emergency occurs. The mobile carrier uses a portable power supply so that it can move freely and easily shifted. To meet these requirements, the driving power of the carrier a motor of 24-volt dc with 250 watts. The radioactive source uses a driving power of 12-volt dc motor with a minimum lift power of 5 kg. The control module designed uses a microcontroller with an android application-based interface that is connected by wireless. In the android application there are virtual numbers and input buttons to give commands to the control module. The application can also receive carrier speed information and the height of the radioactive source. To break the power of driving motor of carrier and the driving power of the lifter of the radioactive source, the mobile carrier uses two-level relays, namely low current conductivity relays and relays with high current conductivity. Next in order to move forward and backward automatically, at each end of the carrier is equipped with a limit switch. The button and top position barriers on the radioactive source lifter use a limit switch.
Assessment of heavy metals concentration in the water around the area of Adipala Cilacap steam power plant using neutron activation analysis
Authors: Rozana K , Sukirno  , Prabasiwi D S , Murniasih S 
Published: February 2020

Abstract
This research was conducted to assess the concentration of hazardous heavy metals (Cu, Zn, As, Cd, and Cr) in water wells and rivers, around the Adipala Cilacap steam power plant, using neutron activation analysis method. Sample of wells water and river water were taken around the Adipala Cilacap steam power plant. Samples were irradiated with pneumatic facility and Lazy Suzan in the Kartini Research Reactor, at a thermal neutron flux of approximately 0.58x1011 n.cm−2.det−1. The average concentration of hazardous heavy metals has the smallest metal value of Cr with a value of 0.0006 mg/L and the highest metal Cu with a value of 0.057 mg/L, which is examined in water wells following a decrease in the order of Cu > Zn > As > Cd > Cr. The five hazardous heavy metals under the maximum standard recommended by the WHO/USEPA and Minister of Health’s Regulation No. 492. In addition to the hazardous heavy metals, there are 13 other heavy metals that determined its concentration (Al, Ba, Mg, K, Fe, Na, Mn, Ti, La, Ce, Sm, Cs, and V), and obtained the results of the metal concentrations Al exceeds the threshold allowable by Minister of Health’s Regulation No. 492 the Year 2010.
Preparation of bacterial cellulose-based adsorbent by simultaneous irradiation method: synthesis and characterization
Authors: Oktaviani Oktaviani , Puspitasari Tita , Pangerteni Dewi Sekar , Indriyati Indriyati , Yunus Ade Lestari 
Published: February 2020

Abstract
The adsorbents based on bacterial cellulose matrices, i.e. bacterial cellulose-co-(poly)acrylamide (BC-PAAM) and bacterial cellulose-co-(poly)acrylic (BC-PAA) has been successfully synthesized using polymerization radiation technique by gamma rays. The irradiation doses used in this study were 25, 50, 75, 100, and 150 kGy, with the dose rate of 5 kGy/h. The results showed that the optimum dose for synthesizing the BC-PAAM by using the simultaneous technique was 50 kGy, with the optimum gel fraction was 90.04 % obtained for mass ratio among acrylamide (AAM) and bacterial cellulose (BC) was 1:4. Meanwhile, the optimum dose for synthesizing the BC-PAA by using the similar technique was 75 kGy, with the optimum gel fraction was 94.27 % for the mass ratio between acrylic (AA) and bacterial cellulose (BC) was 2:3. The Fourier Transform Infrared spectroscopy (FTIR) spectra showed that the AA and AAM had been successfully grafted onto the BC. The increasing of heat resistance of the grafted adsorbent was indicated by Differential Scanning Calorimetry (DSC) analysis.
Application of thomas fermi model on the study of the transition phase from the inner crust to the core of neutron star
Authors: Lathifa I , Sulistyani E T 
Published: February 2020

Abstract
The study of the Thomas Fermi model and its application on the study of the inner crust of neutron star has been done in order to explain pasta phase (the geometric structure changing of atomic nuclei from spherical ones to homogenous liquid) on the transition area from the inner crust to the core of neutron star. The study was carried out by the Wigner Seitz approach on the inner crust that is obtaining the total energy equation as a function of the density of the system, as a Thomas Fermi’s model. In this study Thomas Fermi’s model explains atomic nuclei that consist of Fermion gas in a system of functional total energy to density by taking into account the contribution of kinetic energy, potential energy and the contribution of interactions between particles. The energy state equation obtained was used to explain the effect of increasing density on the inner crust energy and explain the pasta phase through the interpretation of the graph of Thomas Fermi energy per baryon as a function of baryon density for every geometric structure of atomic nuclei.
Synthesis of Zirconium Oxychloride and Zirconia Low TENORM by Zircon Sand from Landak West Kalimantan
Authors: Poernomo H , Sajima  , Pusporini N D 
Published: February 2020

Abstract
In order to enhance the added value of zircon minerals (ZrSiO4) derived from tailing gold mining in Mandor, Landak, West Kalimantan; the hydrometallurgical process is needed to obtain zirconium products such as zirconium Oxychloride (ZrOCl2.8H2O) and zirconia (ZrO2). Zirconium products that are sold must meet the requirement of Technologically Enhanced Naturally Occurring Radioactive Material (TENORM) or (ThO2 + U3O8) is below 500 ppm. The purpose of this research was to process zircon sand with TENORM content 1784 ppm to be ZrOCl2.8H2O and ZrO2 low TENORM. Zircon sand processing has been carried out through melting zircon sand with NaOH to bind Zr became Na2ZrO3 and Si as the impurities to become Na2SiO3, water leaching to separate Na2ZrO3 from Na2SiO3 and other impurities, acid leaching (HCl) to convert Na2ZrO3 to be zirconium oxychloride low Si (ZOC-1) then ZOC-1 to be zirconium sulfate base (ZBS), ZBS then being deposited to be ZrO(OH)2, ZrO(OH)2 converted to be zirconium oxychloride low TENORM (ZOC-2), ZOC-2 then being crystallized to be ZrOCl2.8H2O and calcinated to be zirconia. The results showed that zircon sand from Mandor, Landak, West Kalimantan could be synthesized into ZrOCl2.8H2O with NORM 1.2586 ppm and zirconia with NORM = 3.5511 ppm, both products have met the industrial-grade requirement.
Gas flow control design vapor deposition in chemical facilities
Authors: Dermawan T , Priambogo N P , Rianto S 
Published: February 2020

Abstract
Design of gas flow control in LabVIEW based chemical vapor deposition facilities. To make the TRISO layer in nuclear fuel, argon, acetone, MTS, hydrogen and propelling gas are used. Currently, the regulation of gas flow in fluidized bed chemical vapor deposition facilities is done manually. Coating by adjusting the flow rate of 2 different gas alloys. The system is designed to obtain a proper coating, using Arduino to control the servo motor which regulates the gas valve. The results obtained that the valve can rotate between the range of 0 degrees to 180 degrees, with the addition of 0.5 degrees per step.
Testing and evaluation of velocity selector control system of small angle neutron scattering spectrometer
Authors: Suparno N , Bharoto  , Patriati A 
Published: February 2020

Abstract
Testing and evaluation of velocity selector control system of small angle neutron scattering (SANS) spectrometer has been done. It applied a unit of speed control variable AC, Optidrive Invertek Drives. This system is designed to be manually controlled and computerized. To control the Optidrive in manual mode, it can be done by keypad on the unit. The Optidrives can be controlled using computer by connecting the unit into a computer via USB port and OptiTools Studio software. Optidrive Invertek Drives need alternative current (AC) voltage one phase 220 volt with three phase out 220 volt. This out voltage is used as voltage source for moving the motor of disk in SANS neutron velocity selector. The speed of the disk in SANS neutron velocity selector is changed by adjusting the frequency from the Optidrive Invertek Drives. The numbers of speed of the disk determine the neutron wavelength passed through SANS neutron velocity selector. It is observed that every increasing frequency of 1 Hz, it will increase the disk speed by 59.929 rpm. The calibration that has been done for this system using silver behenate, obtain wavelength of the neutrons dependent to the disk speed. They are 3.10, 3.09, 3.41, 3.76, 4.23, 4.71, and 5.39 Å for disk speed 6500, 6000, 5500, 5000, 4500, 4000, and 3500 rpm respectively.
Performance analysis of digital X-ray radiography system in radiometallurgy installations for pebble bed fuel imaging
Authors: Ismarwanti Sri , Rahmatullah Helmi Fauzi , Artika Refa , Sigit Rohmad , Ajiriyanto Maman Kartaman , Setiawan Jan 
Published: February 2020

Abstract
Research and studies on pebble bed fuel to support the realization of RDNK based on HTGR have been carried out by BATAN. Indicators of reliability of nuclear fuel are able to fulfill the criteria for irradiation testing and qualify in post irradiation tests. At present, Radiometallurgy Installation as a post irradiation examination location has completed installation of X-ray radiography equipment for non-destructive testing. Performance analysis includes the function of tools and the completeness of test support facilities. Digital X-ray radiography has a maximum voltage capability of 320 kV. X-rays are directed vertically towards the sample and sensor film. X-rays captured by film sensors can be seen directly in real time on a computer. To put the pebble bed fuel is provided a special holder. The X-ray radiography system trials were carried out on a pebble bed fuel model. The purpose of the trial to find out the performance of X-ray radiography systems in capturing the image of the pebble bed fuel model. The fuel model is made of ceramic which simulates graphite and lead material that simulates TRISO. The results obtained indicate that the X-ray digital radiography system is able to capture the image of the pebble bed fuel model with a good image.
Ouw Natural Clay-Titanium Oksida (LaO-TiO2) Composite Adsorption Ability On Lead (Pb) Metal
Authors: Bijang C M , Nurdin M , Azis T , Sekewael S J , Wattimena H 
Published: February 2020

Abstract
Research has been conducted to synthesize and characterization composite LAO-TiO2 based on LAO mass variation and calcination temperature and its application as an adsorbent of lead metal (Pb). Characterization is done using X-Ray Diffraction (XRD) at an angle of 2θ: 5-60° of LAO mass variation for pillarization, which are 2, 3, and 5 with calcination temperature of 200, 250 and 300°C. The testing of the composite LAO-TiO2 as lead (Pb) metal absorbent using Atomic Absorption Spectroscopy (AAS). The result shows the most significant basal spacing (d-spacing) is on mass variation 5 g (K5) after calcination with temperature 200 10.19 Å. Composite LAO-TiO2 Application as lead (Pb) metal adsorbent shows the adsorption capacity (Q) obtained ranges from 4.4-4.9 mg/g.
Antioxidant and Anticancer Activity Tests of “Pasote” Leaf Water Extracts (Dysphania ambrosioides L.) by In Vitro Method in Leukemia Cancer Cells
Authors: Pandiangan D , Lamlean P Y , Maningkas P F , Nainggolan N , Unitly A J A 
Published: February 2020

Abstract
The purpose of this study was to obtain research information about the anticancer and antioxidant potential of Pasote leaf powder extract. Anticancer testing was carried out by the MTT test method on P388 leukemia cells. The antioxidant test was carried out by the DPPH method and determined by UV-Vis Spectro at a wavelength of 517 nm. Data analysis with the Origin Lab program for anticancer, and Excel programs for antioxidant data analysis. Pasote water extract has anticancer activity potential category as an anticancer with IC50 of 0.105 μg / mL. The results of the antioxidant testing of Pasote water included in the medium category with an IC50 value of 50.736 µg/mL. This shows that Pasote leaf water has the potential to be made antioxidant and is not different from antioxidant vitamin C. The conclusion is Pasote leaf water has the potential to be used as an anticancer and antioxidant.