Atom Indonesia (E-Journal)
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Assessment of Individual Radiosensitivity in Inhabitants of Takandeang Village - A High Background Radiation Area in Indonesia
Get PDFPeople living in high background radiation area (HBRA) possibly developed the radioadaptive response (RAR) phenomena. Mamuju area in West Sulawesi Indonesia also known as the HBRA in Indonesia due to high natural uranium contents. It is possible that RAR was developed in Mamuju inhabitants. To prove this hypothesis, here in this study evaluation of the individual radiosensitivity in Takandeang Village, Mamuju inhabitants using G2 micronucleus (MN) assay was conducted. Association between blood groups and TP53 Arg72Pro polymorphism with individual radiosensitivity also evaluated in this study. Using G2 MN assay we assessed the individual radiosensitivity of Takandeang Village inhabitants and control samples. For each sample, three parameters were calculated. The spontaneous (baseline) MN number, MN number after 0.5 Gy in vitro irradiation and radiation induced MN were calculated to predict the individual radiosensitivity. The radiation induced MN was defined by subtracting the spontaneous MN number from the MN number after irradiation. The mean and SD of the number of micronucleus induced by radiation found in control group (CG) was set as the cut-off value to determine the individual radiosensitivity in all samples. The radiation induced MN higher than the mean CG + 1SD CS was scored as 1, indicating a milder radiosensitive phenotype, whereas a result higher than the mean CG + 2SD CG was scored as 2, and indicated a more severe radiosensitive phenotype. When the individual value was lower than the mean CG + 1SD CG, a score of 0 was attributed to the tested subject. Results showed that four individuals in Takandeang Village inhabitants were having a milder radiosensitive phenotype, whilst the other was categorized as normal radiosensitive. The similar finding also found in control samples. Our study failed to find a correlation between radiosensitivity and blood group also the TP53 Arg72Pro polymorphism. Overall our study revealed the possibility of RAR phenomena in Takandeang Village inhabitants. Further investigation using a different point of radiation dose value and larger sample number should be performed to validate this study results.
Assessment of Human Milk Intake by Breastfed Infants Using Deuterium Oxide Dose-to-Mother Technique in “Tumbuh Kembang Anak” Cohort, Indonesia
Get PDFIndonesia government has done the WHO recomendation that the infants should be exclusively breastfed for the first six months of life to achieve optimum growth, development and health. Nevertheless, the percentage of exclusive breastfed infants have not achieved the target yet and has not been scientifically quantified. The objective of the study is to measure the intake of human milk of Indonesian infants during first 6 months and to record the breastfeeding practices of mothers. Thirty healthy mother-infant pairs were recruited randomly for the cross-sectional study at “TumbuhKembangAnak” cohort in Bogor. Milk intake to the infant was measured using the deuterium oxide technique over 14 days. The interviews were done by members of team using the questionnaire to get the information on breastfeeding practice of respondents. The results showed that intake of human milk was 784 ± 117g.d-1 (mean ± SD), 787 ± 180 g.d-1 for infants 3 and 6 moths of age. It showed that the milk intake were not different between 3 and 6 months. The body composition of mothers, age, or parityhad no effects on milk intake of infants, education of mothers (3 months aged, P = 0.061, r = -0.097 and 6 months, P = 0.616, r = -0.095), infants of3 months aged, P = 0.200, r = -0.290 and 6 months, P = -0.078, r = 0.684). Body mass index of mother (P 0.05, r = 0.963) were correlated with the milk intake. About 53 % of the lactating mothers started breastfeeding within less than one hour of delivery. Breast-milk intake of the Indonesian infants were documented using deuterium oxide-to-the-mother technique.In the current study concluded that the exclusive breastfeeding practices with 30 pairs of mother-infant still shows that the conditions of exclusive breastfeeding practices have not been properly adhered to by mothers who deliver babies. It is recommended that "mother and baby health officer" in Indonesia are increasingly promoting in order mothers in urban and rural areas to breastfeed exclusively for up to 6 month
Experimental and Numerical Simulation Investigation of Single-Phase Natural Circulation in a Large Scale Rectangular Loop
Get PDFIn order to anticipate station blackout, the use of safety system based on passive features is highly considered in advanced nuclear power plant designs, especially after the Fukushima Dai-ichi nuclear power station accident. An example is the application of natural circulation in the emergency cooling system. To study the reliability of such an application, a research project on natural circulation was carried out. This paper describes the investigation results on the natural circulation phenomena obtained using a large rectangular experimental loop named FASSIP-01. The experiments were conducted at two different heat source powers. The experimental results are analysed using existing correlation and numerical model simulation. The RELAP5 system code is applied to model the natural circulation. FLUENT computational fluid dynamic code is used to visualize the flow distribution. The experimental results show the establishment of stable natural circulation in all heat power input with the mass flow rate of about 0.0012 kg/s. Calculation using the existing correlation shows that the experimental Reynold numbers are lower than predicted by the correlation. The computational fluid dynamics-based tool could show the three dimensional distribution of the temperature, while the model of RELAP5 predict well the dynamic of the single-phase natural circulation established in the experimental loop. It is concluded that the stable natural circulation have been established in the large rectangular loop and the model of the RELAP5 could simulate the observed natural circulation phenomenon reasonably well
Interaction of 137Cs with Sumedang Clay as Natural Barrier of Radwaste Disposal
Get PDFThe interaction of 137Cs with Sumedang clay as a natural barrier for radwaste disposal system has been studied. The initial concentration of Cs was 10‑8 M for the experiments on the contact time and the effect of Na and K concentrations on the sorption of 137Cs; however, the initial concentration ranging from 10‑8 to 10‑3 M of CsCl in the solution for the effect of CsCl concentration. The distribution coefficient Kd is used as the indicator of 137Cs sorption into samples. It was found that the Kd values decreased nonlinearly with the concentration of Na and K, and also to the effects of CsCl concentration. A Freundlich isotherm was proposed to explain the sorption phenomena observed in the experiment. Conclusion of the experiments shown that the presence of metal ions such as Na+ and K+ and variation of CsCl concentrations in the solution have a significant effect on the sorption of 137Cs to the samples. The results should be taken into account for the assessment or selection of the site of radwaste disposal facility in the future
The Role of BNCT in Breast Cancer Treatment
Get PDFBoron neutron capture therapy (BNCT) is a promising future technique of breast cancer therapy. BNCT is a cell-targetting therapy. In BNCT, the use of boron-10 combined with curcumin analog will provide selective radiation therapy only to breast cancer cells, whereas healthy cells will not be affected. This is because the alpha radiation from the boron-10 nuclei that fission due to thermal neutron irradiation only has a short range of between 4 and 9 μm, whereas the cell diameter is between 10and 20 μm, so the reaction is limited only to the cancer cells. If the development of BNCT succeeds, then in the future the malignancy of the breast cancer will be effectively treated by cancer-cell targeted therapy, thereby avoiding the side effects of conventional therapy
Investigation on Neutron Flux Effect onto Irradiated Fuel Burn-up Stored in the Reactor TRIGA PUSPATI
Get PDFAn investigation on the out-core neutron flux in the Reactor TRIGA PUSPATI is carried out in this work to determine whether the thermal and/or fast neutron from the core would cause burn-up of the irradiated fuel stored in the same vicinity of the reactor core. The storage rack is positioned at 1 m from the central thimble.MCNPX code is used to calculate the fast and thermal neutron flux at 750 kW reactor power using 10 cm x 10 cm x 10 cm mesh while MATLAB model on 20 cm x 20 cm mesh model is used to plot the axial and radial distribution of the neutron flux density. The results show that the thermal neutrons occurred at energy lower than 1 x 10-6 MeV and traveled to a maximum distance of 78 cm. The greatest flux for thermal and fast neutrons is 1 x 1013 n.cm2.s-1 and 5 x 1013 n.cm2.s-1 respectively. The fission-rate of the fuel in the core is determined to be 3.18 x 1014 particle/s compared to 1.51 x 107 particle/s of the irradiated fuel in the storage rack. The burn-up of the fuel in the storage rack is in the order of micrograms and therefore is negligible. It is concluded that neutron flux from the core would not impart burn up effect onto the irradiated fuel stored at the storage rack in the reactor pool
Antiproliferative Activity of Extracts and Fractions from Irradiated Curcuma zanthorrhiza Rhizomes Against Mouse Leukemia and Human Cancer Cell Lines
Get PDFCurcuma zanthorrhiza Roxb. is a medicinal plant that is used as a raw material in the herbal medicine and pharmaceutical industries. The main content of C. zanthorrhiza is curcuminoid, which is used as an antioxidant and an anticancer agent. The aim of this research was to study the effect of gamma radiation used for preserving simplicia or herbal drugs through the examination of their cytotoxicity against mouse leukemia L1210 cells and antiproliferative activity against human cancer cell lines HUT78, A549, HeLa, and THP1. The samples of curcuma rhizome were irradiated by gamma ray emitted by Cobalt-60 as a source at doses of 0 (control), 5, 7.5, 10, and 15 kGy. After irradiation, the samples were macerated using n-hexane, ethyl acetate, and ethanol, respectively. Preliminary cytotoxicity test toward extract from control sample against mouse leukemia L1210 cells revealed that the ethyl acetate extract was the most active extract inhibiting the growth of cells with an IC50 value of 16.6 µg/mL, followed by ethanol extract (18.8 µg/mL) and n-hexane extract (42.7 μg/mL). Fractionation using a chromatography column of the ethyl acetate extract resulted in seven fractions denoted as F1-F7. The cytotoxicity test of the seven fractions against mouse leukemia L1210 cells showed that fraction 3 (F3) was the most active fraction with an IC50 value of 10.0 μg/mL, followed by F7 (11.2 μg/mL), F6 (11.8 μg/mL), F5 (12.0 μg/mL), F1 (13.2 μg/mL), F4 (14.5 μg/mL), and F2 (27.8 μg/mL), respectively. Based on these results, all irradiated samples were then extracted, fractionated, and tested for cytotoxicity in a similar manner. The result showed that irradiation of samples under doses up to 10 kGy can be used to preserve Curcuma zanthorrhiza simplicia without damaging its efficacy. To ensure that the irradiation dose of 10 kGy did not reduce anticancer activity, the F3 from the irradiated sample at a dose of 10 kGy was also examined of its in-vitro antiproliferative activity using HUT78, A549, HeLa, and THP1 human cancer cell lines. The results showed that irradiation of the sample at a dose of 10 kGy reduced the antiproliferative activity of F3 against HUT78 (32 %), A549 (48 %), HeLa (42 %), and THP1 (31 %). However, its reduction did not eliminate its antiproliferative activities. These results indicated that the preservation of simplicia using radiation can be done at a maximum radiation dose of 10 kGy by modifying the concentration of simplicia in the fabrication process of herbal medicine formulation
Early Lung Cancer Detection Using Artificial Neural Network
Get PDFLung carcinoma is a malignant lung tumor that is deadly and is characterized by the uncontrolled cell growth in the tissue of lung. Normally the lung cancer detection is done by visual inspection of x-ray image by medical doctor. The purpose of this study is to create a computational tool that can automatically detect early lung cancer from x-ray image. This research has two main steps, with first being to characterize cancer or cancer symptoms based on x-ray images and second step is to develop an artificial neural network (ANN). In first step, particularly it is wanted to lay out a rigorous image processing framework with sequential steps: (i) image noise reduction, (ii) image enhancement, (iii) lung organ segmentation, (iv) object edge detection, and (v) tumor boundary detection. The framework incorporates image processing techniques such as thresholding and morphological detections (erosion and dilation). The framework is expected to reveal the relevant features that define lung cancer or early lung cancer such as area, perimeter, density profile and shape ratio. For the second step, the ANN is built based on machine learning algorithm to study a large set of x-ray images of positively diagnosed lung cancer patients. In addition to learning solely based on the 2D x-ray images, it is also incorporated the previously studied tumor features. The two combined with a large dataset is expected to enable the machine to reach a close to 100 % detection accuracy. Based on the test results of 10 samples obtained the comparative value of the calculated by the ANN with the results of measurement with Matlab program is tends to approach the same. It can be concluded that ANN has been successfully educated so that can identify 10 samples correctly
Evaluation of Kidney Dose in Neuroendocrine Tumors Patients after Peptide Receptor Radionuclide Therapy using 177Lu-DOTATATE
Get PDFRadiation dose to the kidneys (kidney dose) in 177Lu-DOTATATE - Peptide Receptor Radionuclide Therapy(PRRT) is considered to be the main potential side-effect from the treatment. Prospective assessment of kidney radiation dose can be made with SPECT, however, this requires an intensive imaging regime over a number of days. For this reason, a retrospective investigation of kidney uptake using quantitative SPECT was performed. The aim of the study was to compare the estimated radiation dose to kidneys for each cycle. Seventeen patients treated with 177Lu-DOTATATE for metastatic neuro-endocrine tumors had full imaging for each of their treatment cycles on a Siemens Intevo SPECT/CT gamma camera. One course of treatment consisted of 3 or 4 cycles approximately 8 weeks apart spanning 6 months. SPECT/CT scans of the abdomen were acquired at 3 time points (4, 24 and 96-120 hours) after administration of ~7.8 GBq of 177Lu-DOTATATE. Nine patients received three cycles in total and eight patients had four cycles. Volumes of interest (VOIs) were defined on a CT scan co-registered with the SPECT images and repeated over all time points, to give the radioactivity in the kidneys. Whole organ dosimetry was estimated using OLINDA/EXM using an exponential clearance model. This gives an estimate of radiation absorbed dose to kidneys, in the unit of absorbed dose of organ per administered activity(Gy/GBq) for each treatment cycle. The mean of the 3 or 4 cycles and variation can then be determined. The result shows that the average kidney radiation dose was 0.23 Gy/GBq (range: 0.06 – 0.42) and the average variation between cycles for all subjects expressed as a percentage was (12.5±7.8) % (median: 11.4 %, range: 1.8 % - 29.4 %). From this study, it can be concluded that the estimated radiation dose to the kidneys for PRRT shows good reproducibility (typically 20 % variation) within an individual across all cycles within one course of treatment (up to 4 cycles). The errors introduced by assuming that the dosimetry estimate per unit GBq administered from the initial cycle could be used for subsequent cycles within a course are unlikely to contribute significantly to the overall estimate of radiation burden and are considered to be safe