Siwabessy Reactor Research Articles

Radionuclide characterization and handling strategy of irradiated Fission Product Material (FPM) capsule waste from molybdenum-99 production

Abstract Irradiated FPM Capsule waste is one of the types of radioactive waste generated from Molybdenum-99 (99Mo) production. This 99Mo is a 99mTc parent radionuclide that is used for the diagnosis of human organ disorders. In its production, the capsule is used for the emplacement of uranium target for irradiation in the GA Siwabessy Reactor. Since the beginning of production until now, the irradiated FPM capsules waste are still being stored in the hot cells because no data on their characteristics and handling systems that are necessary for their treatment. However, long-term storage of the FPM capsules waste in the hot cells shall be avoided because it can disrupt the production process of 99Mo and pose radiation risk to workers. The objectives of this research are to characterize radionuclides composition in the FPM capsule waste and identify its appropriate handling system. The radionuclides characterization was carried out using ORIGEN 2.1 software whereas the selection of the handling system was based on the suitability or modification of the available facilities at Radioactive Waste Management Installation (RWMI)-BRIN. The characterization results show that up to a decay time of 50 years, an FPM capsule waste contains activation product radionuclides such as 55Fe, 59Ni, and 63Ni with a total specific activity of 7.11x106 Bq/g. Three FPM capsule waste handling systems were identified that can be implemented at the RWMI facility, namely by using a 350 -liter concrete shell and then storing in an interim storage for low and intermediate-level waste, using a 60-liter stainless-steel canister which is then stored in the interim storage pit for high-level waste, or by modifying the interim storage pit for high-level waste. Radionuclide characterization and appropriate handling systems are required for the safe management of irradiated FPM capsule waste. This FPM capsule waste management is important for human and environmental protection.

A SIMULATION OF IRRADIATION CALCULATIONS ON LUTETIUM-177 PRODUCTION IN RSG-GAS USING U3SI2-AL AND U9MO-AL FUELS

This research is a simulation of irradiation calculations on the production of the radioisotope Lutetium-177 (177Lu) in the G.A Siwabessy Reactor (RSG-GAS). This study aims to analyze the comparative calculation of 177Lu activity and its purity. One of the production methods of 177Lu in RSG-GAS is carried out by irradiating Lu2O3 targets. This Lu2O3 target irradiation produced the radioisotope 177Lu along with 177mLu as an impurity. For Medical treatment using radioisotopes, the minimum activity for 177Lu is 20 GBq/mg, and the impurity should not exceed 0.1%. Calculations were carried out with thermal neutron flux input at 15 MWt operational power for the RSG-GAS core with U3Si2-Al fuel (density 2.96 gU/cc and 3.55 gU/cc) and U9Mo-Al fuel (density 3.55 gU/cc). Calculations were carried out by simulating 8 days of irradiation using ORIGEN2.1. The results showed that the 177Lu activity resulting from irradiation of Lu2O3 targets at various CIP positions in the U9Mo-Al reactor core was larger than that of the U3Si2-Al core. Until the 30th day, the 177Lu product resulting from irradiation on the U3Si2-Al and U9Mo-Al cores still meets the minimum value of 20 GBq/mg for treatment needs in nuclear medicine, with the activity value of 177Lu resulting from irradiation on the U3Si2-Al core ranging from 241-403 GBq/mg, while the activity of irradiated 177Lu in the U9Mo-Al core ranges from 335-561 GBq/mg. In addition, until the 30th day of decay, 177Lu has a percentage value of 177mLu irradiated in the U9Mo-Al and U3Si2-Al cores of 0.0346% and 0.0344%, respectively. The results are still below the maximum impurity value of 0.1% and thus safe to use as a therapeutic agent. Keywords: 177Lu, Activity, RSG-GAS, ORIGEN2, Irradiation

Identification and tracing of radionuclides in low- and medium-activity liquid radwaste sources of G.A. Siwabessy reactor

Abstract The liquid radioactive waste generated by the G.A. Siwabessy reactor (RSG-GAS) is categorized into low-activity liquid radwaste (LALR) and medium-activity liquid radwaste (MALR). The radionuclide content of both LALR and MALR can use as an indicator of the structural integrity of the reactor’s systems, structures, and components (SSC). To evaluate the degradation of the reactor SSC, the radionuclide species were identified, and their activities were measured using gamma spectroscopy. Based on the identified radionuclides, the process of their formation can be traced. The radionuclides identified in LALR were 24Na, 51Cr, 59Fe, 60Co, 65Zn, and 124Sb, while the radionuclides in MALR were 24Na, 51Cr, 58Co, 59Fe, 60Co, 65Ni, 65Zn, 89Kr, 90Kr, 109Cd, 131I, 132I, 140Ba, 137Cs, 146Ce, and several others. The radionuclides found can be classified into corrosion product activation (60Co, 65Zn, 51Cr, 59Fe, 24Na, 65Ni), topaz impurities activation (51Cr, 59Fe, 60Co, 65Zn), fission product (90Kr, 140Ba, 131I, 137Cs, etc.), and demineralized water impurities activation (51Cr, 59Fe, 65Zn, 60Co, etc.). After comparing the activity value of each radionuclide with the limit value in the safety analysis report document, we can conclude that the activity of each one is below the required level. It can infer that the structural integrity of reactor SSC is still well maintain. During routine monitoring, the radionuclide content in the primary coolant fluctuates depending on the reactor load. The concentration of radionuclides detected varies when a large or small number of research samples are loaded onto the core. Nevertheless, their activities remain within the required safety limits.

Study Characteristics of a Multipurpose Reactor Building G.A. Siwabessy using Floor Spectral Ratio

The G.A. Siwabessy Reactor is a vital national object of Indonesia’s nuclear infrastructure. These nuclear facilities are vulnerable to earthquake shocks due to regional tectonic activity. This could have a major impact on society and the surrounding environment if a nuclear disaster occurs. To mitigate hazards, we investigate location and building characteristics through Horizontal to Vertical Spectral Ratio (HVSR) and Floor Spectral Ratio (FSR) analysis. We determine the natural or dominant frequency (f0) and the amplification factor (A0). We carried out data acquisition on 8 - 19 January 2023 using the Lennartz LE-3D/20s short period seismometer. The data collection time was 31 minutes with 100 Hz sampling. We analyzed the data using Geopsy software. The natural frequency range obtained for wave propagation based on the direction of the NS component is in the range 1,423 – 4,726 Hz. For wave propagation in structures with the EW component direction, the f0 value is in the range 1,280 Hz to 9,753 Hz and the average f0 value in this direction is 2,957 Hz. This research will be a reference in the Periodic Safety Assessment regarding the resilience of building structures due to changes in the maximum ground acceleration value as a condition for extending the operational permit for the G.A. Siwabessy reactor.

Analisis Skenario Rencana Kontinjensi Nuklir Tangerang Selatan Menggunakan JRODOS

The scenario of the radionuclide release in the South Tangerang city nuclear contingency plan (2013) uses the GA Siwabessy worst accident scenario, namely the Beyond Design Basis Accident (BDBA). The technique uses a predetermined wind direction and wind speed. However, problems in the field are wind direction constantly changing and may not predict the time of an accident in advance. The objective of this paper is to conduct an initial analysis of the scenario of the radionuclide release in the South Tangerang city nuclear contingency plan using JRODOS decision support software. The study compared the design of the radionuclide release written in the South Tangerang city nuclear contingency plan with the scenario of the radionuclide release from the JRODOS prognosis results. The study used a mixed method and a descriptive and analytical approach. In general, the results show that the prognosis of the radionuclides released by using JRODOS to some extent is similar to the scenario of the radionuclide release of the South Tangerang city nuclear contingency plan, both resulted in an affected area that reaches up to a 5 km radius from the GA Siwabessy reactor. The differences are in the specific affected areas due to different weather data, specifically, wind direction data. According to the condition and parameter used in the study, as discussed in the method section, the results show that the villages of Muncul, Kademangan, and Setu have higher affected risk rather than other towns. Nevertheless, for a more comprehensive analysis, further study is needed by using more event-time scenarios and by selecting the event-time within the range of the South Tangerang city nuclear contingency plan scenario’s event-time. Keywords: GA. Siwabessy reactor, nuclear contingency plan, radionuclide release scenario

Dynamic modeling and controlling of a spent nuclear fuel storage pool under periodic operation and station blackout conditions

The Fukushima incident provided the lesson that spent fuel storage pool (SFSP) require adequate analysis of thermal performance. This study aims to investigate the dynamic behaviors of SFSP under normal- and station blackout (SBO) conditions. The well-mixed approach is utilized and considers the heat and mass transfer processes in developing a dynamic model using Stella software. This dynamic model is validated against experimental data undertaken at the G.A. Siwabessy Reactor SFSP. The model’s predicted results are in good agreement with the experimental data, with a mean relative deviation (MRD) of 0.0085%–0.042% and a mean squared error (MSE) of 0.0006–0.0047. The simulation results show that the cooling system requires additional time operation in the planned addition of spent nuclear fuel (SNF). The survival time under SBO without human intervention for current inventory, addition of 120 SNF, and 60-years reactor operation are 142 days, 104.4 days, and 45.8 days, respectively.

Simulation of microtube irradiation on the beam tubes of GA Siwabessy reactor for in-vitro boron neutron capture therapy

The BNCT in-vitro test using a microtube irradiated in the neutron beam of the RSG-GAS beam tubes has been simulated using PHITS code. The simulation was performed by modeling a microtube containing boron solution which was placed 5 cm in front of the beam tubes. Inside the beam tube was installed a beam shaping assembly (BSA) using 80 cm of MgF 2 as a filter to reduce fast neutron and gamma fluences. Microtube containing 1.5 mL of boron solution with boron enriched 10B of 90%. The microtube dose i.e alpha dose, 7Li dose, proton dose, and gamma dose were calculated for boron concentration of 1 ppm. The simulation of microtube containing 1 ppm boron solution shown that irradiated in the BSA-S5 neutron beam can produce 20 Gy dose in the shortest irradiation time of 2.5 hours.

Safety analysis of the irradiation of Tellurium (Te) target in G.A. Siwabessy Reactor

Safety Analysis of the Irradiation of Tellurium (Te) Target in G.A. Siwabessy Reactor. Providing public service becomes one of the priority programs made by the Head of BATAN, such a program is the radioisotope production of Iodine 131 (I-131), which emits gamma and beta that are utilized for medical purpose. The radioisotope can be produced by irradiating the target of Tellurium dioxide (TeO2) on the G.A. Siwabessy Reactor core. Tellurium dioxide (TeO2) is irradiated on the position of Central Irradiation Position (CIP) D-6 and E-7 because the Irradiation Position (IP) is used for Topaz irradiation and CIP (D-6, E-7) is used for the irradiation of Low Enriched Uranium (LEU). Based on the several safety requirements such as analyze the optimum amount of the Tellurium target on CIP (D-6, E-7) with Topaz and LEU. The scope of the research includes the reactivity disturbance, radial power peaking factor and thermohydraulic disturbance. The diffusion group constant of the model uses the program of WIMSD-5B and the result is used for calculating reactivity disturbance and radial power peaking factor with the program package of BATAN-2DIFF. The thermohydraulic disturbance is calculated with using the Generalized Gap Temperature Calculation (GENGTC) program. The calculation of the reactivity of 750 gram (6x125 gram) Tellurium is resulting the change of negative reactivity of-0.27% Δk/k and the value of radial power peaking factor is 1.34 and the temperature at the center of TeO2 target is 366.7°C and outside the capsule (Aluminum) is 58.39°C, if it is compared to the safety margin of ± 2% Δk/k, PPFrad max=2.6, melting point of Al=660°C, melting point of Te=449.5°C, so all the parameters still meets the safety requirement.

Iodine analysis of foodstuffs samples using epithermal instrumental neutron activation analysis

Iodine is an essential element that has an important role in the proper growth and thyroid hormone functioning of humans. Iodine deficiency was correlated with the health status of human-caused by malnutrition. The analytical method to analyze the Iodine content on foodstuffs is limited because Iodine concentration exists in a level of a trace. 127I has a ratio of I 0 to s relatively high, and it is possible to obtain 128I (t1/2 = 24.5 minutes) using nuclear reaction with an epithermal neutron. Samples were collected at Magelang region, and it consists of foodstuffs that consumed by the citizen. All sample has been dried using Freeze dryer at-90 °C and 0.03 bar for 24-48 hours. After drying, the sample then pounded to get the form of granules smooth, about 100-150 mesh. About 40 to 130 mg of sample was weighed accurately on a clean micro vial of Polyethylene. Irradiation has been carried out at l5 MW reactor power using neutron epithermal for 45 seconds at the rabbit facility of GA. Siwabessy reactor. After cooling 5 to 10 minutes, the irradiated sample then counted for 300 seconds, and the gamma-ray spectra obtained emitted have been analyzed by Hyperlab software. Several standard reference materials of NIST have been used as analytical quality control. The experimental result shows that the Iodine has the Boron ratio, RB, and the Advantage factor, Fadv, equal to 2.4 and 21, respectively. Trace element of Iodine has been determined quantitatively on nine spices, seven types of meat, and 32 vegetables. The Iodine concentration on spices have average 1.57 ± 0.23 mg/kg with range value 0.38 mg/kg to 3.4 mg/kg. Iodine on vegetable have average of 2.00 ± 0.43 mg/kg with range value of 0.38 mg/kg to 7.30 mg/kg. Meanwhile, its concentration on meat has range 0.71 mg/kg to 2.16 mg/kg, with an average of 1.44 ± 0.28 mg/kg, lower than that on vegetables. Epithermal INAA is a reliable analytical technique for Iodine determination quantitatively.

Elemental analysis of SRM 1547 peach leaves, 1573a tomato leaves, and 1570a spinach leaves

Neutron Activation Analysis Techniques more used in determining macro and microcontent in food ingredients. The quality of the test results is needed to produce a valid analysis. To validate the result of the analysis of macro and micro mineral content in food ingredients, quantitative analysis of the elements in the reference standard is NIST SRM 1547 certified Peach Leaves, NIST SRM 1573a Tomato Leaves, and NIST SRM 1570a Spinach Leaves have been done. The Z-score parameter was used as a validation parameter. Elemental with a long half-life was determined quantitatively using the NAA k0 method. The elements were determined quantitatively through long-lived radioisotopes using the k0 Instrumental Neutron Activation Analysis in the G.A Siwabessy reactor. A number of 50 mg-120 mg samples were weighed and irradiated at the neutron flux of 2.5x1013 n.cm−2.s−1. Irradiation was carried out for 3 hours on the rabbit system while counting with gamma spectrometry was carried out after cooling time of 23 weeks. Quantitative analysis was carried out using a soft K0-IAEA device. The results of quantitative analysis obtained elements of Ca, Fe, Zn, Rb, Sr on SRM NIST 1547 Peach Leaves; elements of Ca, Cr, Fe, Co on NIST SRM 1573a Tomato leaves and elements Ca, Sc, Zn, Rb, Sr, Co on NIST SRM 1570a Spinach Leaves with uncertainty <10% (3.26-8.68%). The Z-score value ranges from-1.25 to 0.69 and the relative bias ranges from 0.1 to 6.28%, so the results of the analysis of these elements are valid for testing elements in food.

Texture Analysis on the AZ31 Magnesium Alloy Using Neutron Diffraction Method

The nature of crystalline materials depends on the individual crystal properties and the features of the polycrystalline state. The direction of crystallite orientation (texture) can undergo evolution during casting, processing, deformation, welding, and also heat treatment. Because texture plays an important role in mechanical characteristics and physical behavior, initial characterization before mechanical treatment needs to be analyzed first. The neutron diffraction method for texture analysis has advantages compared to the x-ray diffraction method, because neutrons can penetrate the material up in the order of centimeters (bulk, texture) compared to x-rays which are only on the surface of the material (surface texture). This research uses magnesium alloy, because this alloy is very light, and is widely used in industries, such as the automotive, computers, communication systems and electronics. The magnesium alloy used is AZ31 type. The AZ31 magnesium alloy is selected due to the most ductile and the most popular amongst AZ wrought alloys (Mg-Al-Zn group). Initial characterization using the neutron diffraction method was held away before the welding procedure was taken out. In this study, a texture neutron diffractometer (DN2), BATAN, set at a wavelength of 1.2799 Angstrom was used to characterize AZ31 material. The neutron source is produced by the GA Siwabessy reactor, which operates at a power of 15 MW. From the characterization of the neutron diffraction pattern, four pole figures {100}, (002}, {101} and {102} were taken. From the pole figure analysis, the crystallite orientation (texture) was obtained in the direction of {001} <110>. The highest intensity lies in the basal center (0002), also seen basal fiber {0001} and prismatic fiber {10-10}

Elemental Analysis of Wepal Sample Using INAA In The Framework of The 2017 IAEA Proficiency Test Program

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.

Influence of GA Siwabessy Reactor Irradiation Period on The Molybdenum-99 (99Mo) Production by Neutron Activation of Natural Molybdenum to Produce Technetium-99m (99mTc)

Production of 99Mo by neutron activation of natural Mo in multipurpose reactor GA Siwabessy is an alternative solution to overcome the 99Mo shortage, particularly in Indonesia. The aim of this study is to evaluate the influence of the irradiation period of the reactor on the quality of the produced 99Mo and 99mTc. A natural molybdenum was packed in quartz ampule and aluminium capsule, irradiated in the research reactor for around 100 hours. The 99Mo - 99mTc separation was conducted in Center for Radioisotope and Radiopharmaceutical Technology using zirconium-based material (ZBM). The observed parameters are 99Mo activity, 99mTc yield percentage, adsorption capacity ZBM and 99mTc quality. Both the obtained 99Mo activity and 99mTc yield percentage were influenced by the irradiation period. On the other hand, neither the adsorption capacity of ZBM nor quality parameters of 99mTc were influenced by the irradiation period.

WATER CHEMISTRY ANALYSIS IN RSG-GAS SECONDARY COOLING SYSTEM

The G.A Siwabessy reactor (RSG - GAS) located in the Puspiptek area uses water as a coolant. The water as a coolant will contact directly with the component or structure of the reactor, that a chemical reac- tion between water and those components might cause the possibility of corrosion process. Therefore, cooling water quality will determine the integrity of reactor components or structures. The research described in this paper was conducted in order to monitor the quality of secondary cooling water, so that the water quality specifications is maintained and the reactor can be safely operated. One way to monitor the cooling water quality is by performing analysis into the secondary cooling water and raw water on June 6, 2016. The methodology used was by analysing the pH value using a pH - meter, conductivity value using Conductivity - meter, water hardness analysis, and analysis for some chemical elements such as Cl - , SO 4 2 - , Fe, P using calibrated Spectrophotometer DR / 2400. Corrosion rate of the carbon - steel as the piping material of secondary cooling system under environmental corrosion condition was also analyzed using the Potentiostat. From those performed analysis, the overall measured values are still below the standard values as required in the RSG - GAS safety analysis report document, meaning that the water quality management of the secondary coo - ling system has been well performed so far.

Development of &lt;sup&gt;99&lt;/sup&gt;Mo/&lt;sup&gt;99m&lt;/sup&gt;Tc Generator System for Production of Medical Radionuclide &lt;sup&gt;99m&lt;/sup&gt;Tc using a Neutron-activated &lt;sup&gt;99&lt;/sup&gt;Mo and Zirconium Based Material (ZBM) as its Adsorbent

Molybdenum produced from fission of U-235 is the most desirable precursor for 99 Mo/ 99m Tc generator system as it is non-carrier added and has high specific activity. However, in the last decade there has been short supply of 99 Mo due to several constrains. Therefore, there have been many works performed for development of 99 Mo/ 99m Tc generator system using 99 Mo which is not produced from either LEU or HEU. This report deals with development of 99 Mo/ 99m Tc generator system where zirconium-based material (ZBM) is used as adsorbent of neutron-activated 99 Mo. The system was prepared by firstly irradiating natural Mo in the G. A. Siwabessy reactor to produce neutron-activated 99 Mo. The target was dissolved in NaOH 4N and then neutralized with 12 M HCl. The 99Mo solution was then mixed with a certain amount of ZBM followed by heating at 90°C for three hours to allow the 99Mo adsorbed on ZBM. The 99Mo-ZBM (9.36 GBq of 99 Mo was Mo/ 4.2 g ZBM) was packed on a fritz-glass column. This column was then fitted serially with an alumina column for trapping 99 Mo breakthrough. The columns were then eluted daily with saline solution for up to one week. The yield of 99m Tc was found to be between 53.7 – 74% (n= 5). All 99m Tc eluates were clear solutions with pH of 5. Breakthrough of 99 Mo in 99m Tc eluates was found to be 0.031 ± 0.019 μCi 99 Mo/ mCi 99m Tc (n= 5) which was less than the maximum activity of 99 Mo allowed in 99m Tc solution (&lt; 1 µCi 99 Mo/mCi 99m Tc). Aluminum breakthrough in 99m Tc eluates was found to be less than 10 ppm. The radiochemical purity of 99m Tc in form of Na 99m TcO 4 was &gt; 99%. Radiolabeling of this 99m Tc towards methylene diphosphonate (MDP) kit gave a radiolabelling efficiency of 99%. In summary, a new 99 Mo/ 99m Tc generator system that used neutron-activated 99 Mo and ZBM as its adsorbent has been successfully prepared. The 99m Tc produced from this new 99 Mo/ 99m Tc generator system attained the quality of 99m Tc required for medical purposes. Received: 23 Februari 2016; Revised: 13 July 2016; Accepted: 17 July 2016

Separation of Radiocopper &lt;sup&gt;64/67&lt;/sup&gt;Cu from the Matrix of Neutron-Irradiated Natural Zinc Applicable for &lt;sup&gt;64&lt;/sup&gt;Cu Production

Radioisotope 64 Cu is a promising radiometallic-isotope for molecular-targeted-radiopharmaceuticals. Having a half-life of 12.70 hours and emitting β + -radiation (E β+ = 0.6531 MeV) as well as β - ray (E β- = 0.5787 MeV), it is widely used in the form of biomedical-substrate-radiopharmaceutical for positron emission tomography (PET) diagnosis and simultaneously for targeted radiotherapy of cancer. The potential needs on the availability of 64 Cu-labeled pharmaceuticals for domestic nuclear medicine hospitals lead to a necessity for the local production of carrier-free 64 Cu using BATAN’s G.A. Siwabessy reactor because of the technical and economical constraints in the production using BATAN’s cyclotron. The presented work is accordingly to study whether the radioisotope 64 Cu can be produced and separated from the matrix of post-neutron-irradiated-natural zinc. This study is expected can be further improved and implemented in production technology of carrier-free 64 Cu based on 64 Zn (n,p) 64 Cu nuclear reaction exploiting the fast neutron fraction among the major thermal fraction due to unavailability of fast-neutron-irradiation facility in the BATAN’s G.A. Siwabessy reactor. The solution of post-neutron-irradiated-natural zinc in 1M acetic acid was loaded into Chelex-100 cation exchanger resin column to pass out the Zn/Zn* fraction whereas the Cu* fraction which remained in the column was then eluted out from the column by using 1.5 M HCl and loaded into the second column containing Dowex-1X8 anion exchanger resin. The second column was then eluted with 0.5 M HCl. The collected eluate was expected to be zinc-free Cu* fraction. It was observed from the half-life and the γ-spectrometric analysis that radioactive copper- 64 Cu containing 67 Cu was produced by neutron activation on the natural Zn-foil target and can be separated from the target matrix by the presented two-steps-column-chromatographic separation technique. The radioactivity measurement showed that wrapping the Zn target with cadmium foil increased the activity of radioactive copper and, thus, the Cu*/Zn*-ratio. Received: 28 June 2011; Revised: 21 February 2012; Accepted: 24 February 2012

Testing of a prototype of calibration facility for noble gas monitoring using 41Ar

A prototype of a calibration facility for noble gas monitoring using 41Ar in the PTKMR-BATAN has been tested. The facility was designed in such a way that the standard source of gas can be reused. The radioactive 41Ar source was obtained by thermal neutron reaction of 40Ar(n, γ)41Ar using a thermal neutron flux of 4.8×1013 neutrons per cm2 per second in two minutes on the multipurpose G.A. Siwabessy Reactor (Batan, Serpong, Indonesia). Gamma spectrometry was used to measure the radioactivity and purity of 41Ar. The spectrum of the 41Ar observed yields an energy of 1294keV because of the highest intensity (99.2%). The activity of 41Ar was 2821kBq and 4% of the expanded uncertainty. The time required for 41Ar to reach homogeneity was 7min, and the effectiveness of resuse was 53%.

EVALUATION OF NAA LABORATORY RESULTS IN INTER-COMPARISON ON DETERMINATION OF TRACE ELEMENTS IN FOOD AND ENVIRONMENTAL SAMPLES

Inter-comparison program is a good tool for improving quality and to enhance the accuracy and precision of theanalytical techniques. By participating in this program, laboratories could demonstrate their capability andensuring the quality of analysis results generated by analytical laboratories. The Neutron Activation Analysis(NAA) laboratory at National Nuclear Energy Agency of Indonesia (BATAN), Nuclear Technology Center forMaterials and Radiometry-PTNBR laboratory participated in inter-comparison tests organized by NAA workinggroup. Inter-comparison BATAN 2009 was the third inter-laboratory analysis test within that project. Theparticipating laboratories were asked to analyze for trace elements using neutron activation analysis as theprimary technique. Three materials were distributed to the participants representing foodstuff, and environmentalmaterial samples. Samples were irradiated in rabbit facility of G.A. Siwabessy reactor with neutron flux ~ 1013n.cm-2.s-1, and counted with HPGe detector of gamma spectrometry. Several trace elements in these sampleswere detected. The accuracy and precision evaluation based on International Atomic Energy Agency (IAEA)criteria was applied. In this paper the PTNBR NAA laboratory results is evaluated.Keywords: inter-comparison, neutron activation analysis, trace elements, foodstuff, environmental samples,NAA laboratory

The Performance of Fine Resolution Neutron Powder Diffractometer at PTBIN-BATAN

We describe the performance of a fine resolution neutron powder diffractometer, DN3, which has been installed at the neutron guide (NG2) in the Neutron Guide Hall about 71 m away from the Multipurpose G. A. Siwabessy reactor core. DN3 has a multi-detector system which consists of 32 3 He neutron detectors and soller-type collimation. The resolution curve of the instrument was found to have little variation over a wide angular region. The best resolution is Δ2θ (FWHM) of 0.23º and Δd / d of 5x10 -3 , where 2θ and d are scattering angle and d-spacing, respectively. The instrument provides sample environment of low temperatures using a cryostat having a temperature range of 10-300K. Several experimental results, interlaboratory comparison study and he next activities to improve the performance of DN3 equipment have also been discussed. Received: 15 October 2009; Revised: 12 April 2010; Accepted: 21 April 2010

PEMBUATAN NANOPARTIKEL EMAS RADIOAKTIF DENGAN AKTIVASI NEUTRON

: It was reported that gold nanoparticle could be used for cancer therapy using thermal effect. It is possible to kill cancer cells using radiation of radioisotope. Study on preparation of radioactive gold by neutron activation at central irradiation position (CIP) of G.A. Siwabessy reactor with neutron flux 1.26 x 1014 neutron s-1cm-2 has been carried out. It was revealed that a radioisotop of gold (198Au) was produced by neutron activation from natural gold. Calculation results showed that 198Au with radioactivity of 0.366 Bq, 2.93 Bq, 9.90 Bq and 23.4 Bq was produced for nanoparticle with diameter of 100, 200, 300 and 400 nm by neutron irradiation for 12 days. The saturation factor was 96.5%. After 10 days of decay, the radioactivity was 0.027 Bq, 0.223 Bq, 0.753 Bq and 1.78 Bq in nanoparticle with diameter of 100, 200, 300 and 400 nm. The radionuclide impurities were 108Ag, 110mAg, 64Cu, 66Cu, 205Pb and 209Pb with the total radioactivity was 4.31 x 10-5 % of the total radioactivity of 198Au at the end of irradiation.