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INDONESIA
Atom Indonesia Journal
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Core Subject : Science,
Exist for publishing the results of research and development in nuclear science and technology Starting for 2010 Atom Indonesia published three times a year in April, August, and December The scope of this journal covers experimental and analytical research in all areas of nuclear science and technology. including nuclear physics, reactor physics, radioactive waste treatment, fuel element development, radioisotopes and radio pharmaceutical engineering, nuclear and radiation safety, neutron scattering, material science and technology, as well as utilization of isotopes and radiation in agriculture, industry, health and environment.
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Articles 11 Documents
Search results for , issue "Vol 45, No 3 (2019): December 2019" : 11 Documents clear
The Effect of Gamma-Irradiated Nitrate-Reducing Bacteria in Decreasing the In Vitro Production of Methane by Buffalo Rumen Liquid R. Rahmani; M.R. Pikoli; I. Sugoro
Atom Indonesia Vol 45, No 3 (2019): December 2019
Publisher : PPIKSN-BATAN

Show Abstract | Download Original | Original Source | Check in Google Scholar | Full PDF (9.852 KB) | DOI: 10.17146/aij.2019.1006

Abstract

Ruminant livestock undeniably contributes to the increase of greenhouse gases by emitting methane. One strategy used to reduce methane emission is by applying nitrate-reducing bacteria (NRB). Utilizing active NRB has a side effect of acidosis in rumen liquid in an uncontrolled condition. Alternatively, NRB can be applied in an inactive form. The aim of this study was to examine the use of gamma irradiation on NRB to be used for decreasing methane production by buffalo rumen liquid. The examination was performed in vitro and involved comparison to other treatments, which were active NRB, autoclaved NRB, and without NRB. The result showed that the NRB in either active or the inactive conditionaffected fermentation of the rumen microorganisms. There were differences in pH values, digestibility of organic matters, ammonia, total and partial volatile fatty acids, and methane production between all treatments after 24 and 48 h of incubation. All treatments showed significant differences for each parameter, except for the gas production (p ≤ 0.05). The irradiated NRB produced slightly more methane, i.e. 3.0 and 10.4 ml/200 mg after 24 and 48 h incubation, respectively, compared to the active NRB, autoclaved NRB, and no-NRB-addition treatments, i.e., 2.0 and 8.0; 7.8 and 11.7; 8.0 and 12.4 ml/200 mg, respectively. In conclusion, the irradiated NRB has a potency as a supplement feed for buffaloes to reduce methane production without the risk of acidosis in the rumen liquid.
Preface Atom Indonesia Vol 45 No 3 prfc prfc
Atom Indonesia Vol 45, No 3 (2019): December 2019
Publisher : PPIKSN-BATAN

Show Abstract | Download Original | Original Source | Check in Google Scholar | Full PDF (1049.853 KB) | DOI: 10.17146/aij.2019.1025

Abstract

Antiproliferative Activity of Extracts and Fractions from Irradiated Curcuma zanthorrhiza Rhizomes Against Mouse Leukemia and Human Cancer Cell Lines E.K. Winarno; H. Winarno; S Susanto
Atom Indonesia Vol 45, No 3 (2019): December 2019
Publisher : PPIKSN-BATAN

Show Abstract | Download Original | Original Source | Check in Google Scholar | DOI: 10.17146/aij.2019.957

Abstract

Curcuma 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.
Acknowledgement Atom Indonesia Vol 45 No 3 ack ack
Atom Indonesia Vol 45, No 3 (2019): December 2019
Publisher : PPIKSN-BATAN

Show Abstract | Download Original | Original Source | Check in Google Scholar | Full PDF (281.148 KB) | DOI: 10.17146/aij.2019.1026

Abstract

Investigation on the Performance of a Wickless-Heat Pipe Using Graphene Nanofluid for Passive Cooling System M.H. Kusuma; N. Putra; A. Rosidi; S. Ismarwanti; A.R. Antariksawan; T. Ardiyati; M. Juarsa; T.M.I. Mahlia
Atom Indonesia Vol 45, No 3 (2019): December 2019
Publisher : PPIKSN-BATAN

Show Abstract | Download Original | Original Source | Check in Google Scholar | Full PDF (314.702 KB) | DOI: 10.17146/aij.2019.761

Abstract

To enhance the thermal safety in case of station blackout, a wickless-heat pipe is proposed as an alternative passive cooling system technology to remove decay heat generation in the nuclear spent fuel storage pool. The objectives of this research are to investigate the heat transfer phenomena in vertical straight wickless-heat pipe using Graphene nanofluid working fluid and to study the effect of Graphene nanofluid on the vertical straight wickless-heat pipe thermal performance. The investigation was conducted in 6 meters height and 0.1016 m inside diameter of vertical straight wickless-heat pipe. In this research, the Graphene nanofluid with 1 % of weight concentration was used as working fluid. The effect of working fluid filling ratio, evaporator heat load, and coolant volumetric flow rate on the water jacket were studied. The results showed that the heat transfer phenomena, which were indicated by an overshoot, zigzag, and stable state, were observed. Based on thermal resistance obtained, it was shown that the vertical straight wickless-heat pipe charged with the Graphene nanofluid has a lower thermal resistance compared to one with demineralized water. The thermal resistance of vertical straight wickless-heat pipe using Graphene nanofluid and demineralized water were 0.015 °C/W and 0.016 °C/W, respectively. While the best thermal performance was achieved at a filing ratio of 80 %, higher heat load, and higher coolant volumetric flow rate. It can be concluded that Graphene nanofluid could enhance the thermal performance of vertical straight wickless-heat pipe.
The Role of BNCT in Breast Cancer Treatment B. Poedjomartono; Y. Sardjono; E. Meiyanto; H. Winarno
Atom Indonesia Vol 45, No 3 (2019): December 2019
Publisher : PPIKSN-BATAN

Show Abstract | Download Original | Original Source | Check in Google Scholar | DOI: 10.17146/aij.2019.936

Abstract

Boron 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.
The Absolute Standardization Methods of 32P for Calibrate Nuclear Medicine Instruments in Indonesia G. Wurdiyanto; H. Candra; H Holnisar; V. Pungkun
Atom Indonesia Vol 45, No 3 (2019): December 2019
Publisher : PPIKSN-BATAN

Show Abstract | Download Original | Original Source | Check in Google Scholar | DOI: 10.17146/aij.2019.905

Abstract

The absolute standardization of 32P radioactive sources employedto calibrate nuclear medicine instruments has been conductedat PTKMR-BATAN. We deemed this activity to be necessarysince 32P used in the nuclear medicine fields has a short half-life, and in order to obtain a result of quality measurement, it requires a special treatment. Moreover, in Indonesia, the use of nuclear medicine techniques has developed rapidly. We prepared all the radioactive sources witha gravimetric method by using a KERN ABT 220-5DMsemi-micro type scale, traceable to the International Unit System. We conductedthe 32P standardization by employing a 4πβ(PS)-γ coincidence method with 60Co as a tracer;meanwhile, we conducted the impurity measurementby employing a beta spectrometer system. The result of 32P absolute measurement was 380.05 Bq/mg with a 0.68-percentrange uncertainty, witha k=2coverage factor. This value was used to calibrate a “Capintec CRC-7BT”dose calibrator that was a secondary standard instrument in PTKMR-BATAN. The results showed us that the calibration factor of the “Capintec CRC-7BT” dose calibrator was 1.12 witha 4.7-percent uncertainty.
Evaluation of Kidney Dose in Neuroendocrine Tumors Patients after Peptide Receptor Radionuclide Therapy using 177Lu-DOTATATE N.R. Hidayati; A. Poon; K. Willowson; E. Eslick; H. Ryu; D.L. Bailey
Atom Indonesia Vol 45, No 3 (2019): December 2019
Publisher : PPIKSN-BATAN

Show Abstract | Download Original | Original Source | Check in Google Scholar | DOI: 10.17146/aij.2019.910

Abstract

Radiation 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.
Cover Atom Indonesia Vol 45 No 3 cvr cvr
Atom Indonesia Vol 45, No 3 (2019): December 2019
Publisher : PPIKSN-BATAN

Show Abstract | Download Original | Original Source | Check in Google Scholar | Full PDF (141.926 KB) | DOI: 10.17146/aij.2019.1024

Abstract

Spectral Comparison of Neutron-Irradiated Natural and Enriched Ytterbium Targets for Lu-177 Production M. Maiyesni; S. Febriana; I. Kambali; D. Kurniasih
Atom Indonesia Vol 45, No 3 (2019): December 2019
Publisher : PPIKSN-BATAN

Show Abstract | Download Original | Original Source | Check in Google Scholar | DOI: 10.17146/aij.2019.930

Abstract

Beta-emitting radioisotope 177Lu has been suggested for radioimmunotherapy, peptide receptor radionuclide therapy, or another radionuclide therapy due to its excellent properties for destroying cancer cells. In this experimental investigation, natural ytterbium (natYb) and enriched 176Yb targets were irradiated with thermal neutrons at 1.2×1014 cm-2s-1 neutron flux for 95 hours. Using a high-purity germanium (HPGe) detector-based spectroscopy system, the post-irradiated targets were measured and the produced radioisotopes were identified according to their gamma ray emissions. Experimental results indicated that several radioisotopes such as 169Yb and 175Yb dominate the post-irradiated natYb target, though a relatively weak intensity of 177Lu was also recorded. In contrast, 177Lu radioisotope dominates the gamma rays observed in the post-irradiated enriched 176Yb target following elution with HNO3 solution. For the first time, evidence is found of 175Yb impurity in the post-neutron-irradiated enriched 176Yb2O3 target as a result of 176Yb(n,2n)175Yb nuclear reaction. This work recommends future 177Lu radioisotope production using enriched 176Yb2O3 target.

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