[en] Measurement uncertainty on analysis of Cs₁₃₇ isotope in the irradiated fuel U₃Si₂-Al of 2.96 gU/cm³ was carries out using gamma spectrometry method. The purpose of this activity is to complement the method validation of Cs₁₃₇ analysis. Traceability measurement is done by using standard isotope of Cs-CRM No.137.4233C and ASTM E320-79 standard method. The components that contribute in determining the uncertainty in the step of sample preparation include sample weighing, dilution and sampling, while in the sample measurement, the components include detector efficiency calculation and measurement of Cs₁₃₇ isotope. The analysis results showed that the uncertainty value of Cs₁₃₇ isotope was 0.0801µg/mL and the uncertainty of Cs₁₃₇ isotope activity was 256.57 Bq/l at 95% level of confidence. (author)

[en] The analysis of uranium (U) content and its impurities in the ammonium uranyl carbonate (AUC) and uranium dioxide (UO_2) produced from research reactor fuel element production installation, PT. BATAN Teknologi have been carried out. Uranium content in the powders was analyzed by potentiometric titration methods and impurity contents was analyzed by atomic absorption spectrophotometer (AAS) and by inductively coupled plasma-atomic emission spectroscopy (ICP-AES). The purpose of this study was to determine of impurity elements in the AUC and UO_2 powder resulting from the production process if it meets the required specifications. It is reported that U content in the AUC is 48.62 wt% and that in the UO_2 is 88.08 wt%. The precision and accuracy analysis of the U content is 0,235% and 0,151%. In case of impurities in the AUC powders, it is reported that the analytical results of Zn, Ni, Cd, Co, Mn, Mg, Fe, Cu and Cr at 10.15 ppm, 1.12 ppm, not detection, not detection, not detection, 0.30 ppm, 216.07 ppm, not detection, and 31.36 ppm, respectively, while that UO_2 are 11.31 ppm, 72.14 ppm, not detection, not detection, 6.25 ppm, 8.65 ppm, 298.24 ppm, 12.75 ppm and 32, 23 ppm. The U and impurity contents in both the AUC and UO_2 fulfill the specification of nuclear fuel for RSG-GAS research reactor. (author)

[en] The analysis method is objected to analyze element that have wavelength 200 nm or below. N₂ gas stream is used to eliminate the influence of air presence in optic system. In this research the pressure of N₂ stream is used variably to get the result of measurements that have low detection limit. The examination steps include the limitation of measurement spectrum, detection limit, standard linearity, and precision test by repeatability test and accuracy test by measurement of standard materials which have concentration at the linear area. The limitation of measurement spectrum is conducted to get good spectrum and measurement accuracy at own wavelength. The detection limit is counted by measuring the intensity of blank solution. Standard Linearity test is conducted by measuring intensity of standard solution for different concentrations. The repeatability test is conducted by repeating the measurements one of standard that therefore it is calculated the chi square value at the used trust value. The good result is obtained at pressure of N₂ stream 20 psi, and the wavelength for As and Sb are 193.759 nm and Sb 206.833 nm. Detection limit for As and Sb are 1.2844 ppm and 1.0785 ppm. Standard linearity for As is obtained from the concentration 1.2844 ppm and 1.0785 ppm. Repeatability for As and Sb present in trust level range 95%, this is based on acceptance value of chi square that be resulted. While precision for As and Sb are 97.81 % and 96.49 %. (author)

[en] Zeolite have the cation can move freely and as exchangeable partly or totally with other cations. Therefore, it can serve the purpose of ion exchanger very selectively to ion cesium which is present in fuel waste. In this research analysis of pore surface area, radius pore, and adsorption have been done. After the characters of Lampung zeolite is known and then analysis of cation exchange capacity (CEC) toward ion ¹³⁷Cs is conducted, analysis of Lampung zeolite adsorption to ion ¹³⁷Cs in waste of fissile product and in research waste is subsequently done. Result of analysis show Lampung zeolite has surface area of 10,0478 m², specific surface area of 47,0841 m²/g, pore radius of 19,3020 ^oA and adsorption of 24,500 cc/g. For application as a ion exchange, Lampung zeolite can adsorb ion ¹³⁷Cs reaching maximum at concentration of CsCl 0,5 N with the contact time 1 day and the optimum KTK value is 0,8360 m eq/g. While Lampung zeolite is able to adsorb 86,4 % ion Cs in waste of fission product. (author)

[en] This Research use parameter of exposure factor are tube current and time (mAs) of CT scan for measuring dose radiation (CTDIw) and image noise with sequence and spiral techniques. The purpose of this research is to know difference of radiation dose (CTDIw) and image noise with sequence and spiral techniques of variation mAs at CT Scan Siemens 6 slice. This research was an experimental study. A five various use of mAs (from 250 mAs up to 290 mAs) and then effect of radiation doses (CTDIw) and image noise due to the techniques being implemented were compared and measured with tested to use paired T-Test to take a conclusion with trust storey level 95 % (ρ value <0,05). That having meaning that there is difference of dose value at sequence and spiral techniques, while test of Wilcoxon at show image noise assess significantly with ρ value equal to 0,000 (ρ value <0,05). It means there are difference of noise image between of sequence and spiral techniques. (author)

[en] It has been done a recovery and analysis of ¹³⁷Cs isotope and heavy elements which are present in the irradiated U₃Si₂-Al fuel plates. The recovery is carried to obtain composition of ¹³⁷Cs, ²³⁵U and ²³⁹Pu isotopes which will be used for burn up calculation. The recovery has been done by cation exchange method with Lampung zeolites. About 150 µL of irradiated U₃Si₂-Al fuel plates solution has been taken and being placed into 4 vials. Moreover, a number of Lampung zeolites have been added into each vial with a variation of weight about 300, 400, 500 and 600 mg. A process of cation exchange has been carried out with a shaker at 200 rpm for 60 minutes and left it for 24 hours. The result of cation exchange process has indicated that there is separation between ¹³⁷Cs-zeolite and U-Pu which present in the liquid phase. The ¹³⁷Cs-zeolite are then weighed and analysed using a spectrometer-alpha. The analysis of U and Pu in the liquid phase has been done by taking 250 µl of supernatant solution and being processed with electrodeposition by using buffer media of (NH₄)₂SO₄ 1 M with a current of 1.2 Ampere and electrode's distance at 10 mm for 2 hours. After the electrodeposition process, the solution has been analysed using spectrometer alpha to obtain the composition of U and Pu isotopes. The results show that the optimum weight of Lampung Zeolites for the separation from heavy elements in irradiated fuel plates is 500 mg. Furthermore, it has been obtained ¹³⁷Cs about 0.0118 µg, ²³⁵U 0.3110 µg and heavy elements 1.5611 µg with a measurement deviation about 0.00001 µg. (author)

[en] This research deals with thermal characterization of AlFe(2,5%)Ni(1,5%) and AlFe(2,5%)Ni(1,5%)Mg(1%) alloys which previously produced. The thermal characterization includes enthalpy analysis, phase change temperature, heat capacity, and heat conductivity. The enthalpy analysis and phase change temperature and heat stability measurement was done using Differential Thermal Analysis (DTA), while the heat capacity measurement was performed by Differential Scanning Calorimetry (DSC) and the heat conductivity measurement was done using Thermal conductometric. The analysis using DTA shows that both alloys has a thermal stability at 650°C. The AlFe(2,5%)Ni(1,5%) alloy underwent 2 steps of thermochemical reaction. The first thermochemical reaction showed the occurrence of heat flow change forming endothermic peak at 656,26°C and at ΔH=56,35 cal/g. The endothermic reaction indicates the melting of Al contained in the AlFe(2,5%)Ni(1,5%) alloy. The second thermochemical reaction occurred at 711,64°C, which indicates that the melted Al directly reacted with Fe and Ni at their eutectic point to form Al-FeAl_3 and Al-NiAl_3. The occurrence of reaction of Al with Fe and Ni was indicated by exothermic thermochemical reaction releasing an amount of heat with approximate ΔH= -13,95 cal/g. The AlFe(2,5%)Ni(1,5%)Mg(1%) alloy, on the other hand, underwent 3 steps thermochemical reaction. The first reaction resulted in endothermic peak at 389,15°C with enthalpy ΔH= 1,13 cal/g. This endothermic reaction indicates that there is a reaction between Mg and N_2 gas contained in the argon used as media for the measurement to form Mg_3N_2. Endothermic reaction also occurred at 654,52°C, which indicates the occurrence of phase change point from α phase to α+ liquid of Al and Mg requiring ΔH= 2,75 cal/g. The third reaction occurred at 562,41°C, which was indicated by endothermic peak. This reaction suggests the burning of Al and Mg to form AlMg with ΔH= 56,22 cal/g. The heat capacity and heat conductivity analysis shows that the addition of 1% Mg may have increased the heat capacity and heat conductivity of both alloys. The heat capacity of AlFe(2,5%)(Ni1,5%) alloy ranged from 0,60 J/g°C at 35°C to 0,90 J/g°C at 450°C, while the heat capacity of AlFe(2,5%)Ni(1,5%)Mg1% alloy ranged from 0,64 J/g°C at 35°C to 0,142 J/g°C at 450°C. The heat conductivity analysis showed that the heat conductivity of AlFe(2,5%)(Ni1,5%) ranged from 235 W/m°K at 25°C to 185,5 W/m°K at 200°C, while the heat conductivity of AlFe(2,5%)Ni(1,5%)Mg1% ranged from 240,4 W/m°K at 25°C to 192,3 W/m°K at 200°C. It is also studied that heat capacity and heat conductivity of both alloys decrease with increasing heating temperature. (author)

[en] "2"3"5U separation has been carried out in the solution of PEB U_3Si_2 - Al with loading of uranium (TMU) 2.96 gU/cm"3 at the Top. Top of PEB U_3Si_2-Al cut into three sections (triplo) with code T_1, T_2 and T_3. Weight of each PEB code T_1 = 0.095 g, T_2 = 0.086 g and T_3 = 0.087 g and dissolved using HCl and HNO_3 in hotcell. The purpose of this study was to determine the content of the isotope "2"3"5U in the solution PEB U_3Si_2-Al post-irradiation and subsequently used for the calculation of burn-up. "2"3"5U isotope separation in the solution PEB U_3Si_2 - Al was conducted using an anion exchange column method using Dowex1x8 resin. Pipette solution of 100 mL, and then put into a column containing Dowex resin with a weight of 1.2 g. U effluent results in the column was eluted using 0.1 M HCl, then dried and conducted electro-deposition process and then analyzed using a spectrometer-α. The analysis showed that the content of the isotope "2"3"5U obtained at T_1 = 0.03665 g/g PEB, T_2 = 0.003468 g/g PEB and T_3 = 0.03208 g/g PEB with separation recovery of 63.71 %. The content of isotope "2"3"5U obtained is used for the calculation of burn-up. burn-up calculation results of PEB U_3Si_2-Al of Top section (T_1, T_2 and T_3) were obtained respectively by 43.31 %, 49.48 % and 45.41 % or burn-up an average of 45.75 %. This data is smaller than a data burn-up of PEB U_3Si_2-Al of middle section of 50.69 % conducted by previous researchers. However, this data can not be used as an input to the reactor, due to should be equipped with a data burn-up of PEB U_3Si_2-Al of bottom section. Therefore, in the next studies will be conducted calculation of burn-up PEB U_3Si_2-Al of bottom section. (author)

[en] Determination of burn-up fuel is one of the most important activities in studying the performance of the fuel in the reactor. The calculation of the burn-up has been done based on the analysis of the fission product, residual uranium and multiply the result nuclides or heavier elements such as plutonium and uranium in the nuclear fuel. This research aims to determine the content of ²³⁵U and isotopes ¹³⁷Cs in post-irradiation Fuel Element Plates (PEB) of U₃Si₂-Al. CsClO₄ deposition method has been used for the separation of isotopes of cesium from uranyl nitrate solution, while for analysing the content of the isotope cesium, a spectrometer-γ was used. Moreover, an anion exchange column method was used for the separation of uranium isotopes and analysis were performed using a spectrometer-α. In the deposition method of CsClO₄, CsNO₃ used as a carrier, while HClO₄ is used for producing a precipitated CsClO₄. In the anion exchange method, uranium has been localized in HCl solution to form a strong acid anion complex, while the other compounds are mixed cations. Uranium was separated using anion exchange column containing Dowex 1x8 resin Cl and HCl was used as the eluent. The uranium which is bounded in the column has been taken by eluting the column using 0.1M HCl. U effluent subsequently has imposed electrodeposition process and been analyzed as ²³⁵U using a spectrometer-α. The content of ¹³⁷Cs and ²³⁵U isotopes in 1 g PEB U₃Si₂-Al density of 2.96 gU/cm³ post-irradiation of 0.0005 g and 0.0277 g. (author)

[en] In this research the precipitation method refers to the ASTM E 320-79 standard, where the precipitate is in the form of CsClO_4 salt. Several aspects related to the precipitation process are studied in order to determine its effectiveness and to obtain relatively nuclear grade of "1"3"7Cs. The precipitation was done by using HClO_4 at 0 °C. The aspects under examination includes the influence of CsNO_3 addition as a carrier and HClO_4 as well as the polarity of the washing agents used. The experiment used "1"3"7Cs standard (NIST) for the determination of detector efficiency, measurement precision and accuracy, and optimum condition during the precipitation process. Measurement for detector efficiency, precision and accuracy was repeated at 5 to 7 times at counting time of 1500 seconds, by which values of (5.31±0.066) x 10"-"2%, 1.119% and 0.542% for detector efficiency, precision bias and accuracy bias respectively was obtained. The optimum addition of the carrier was determined by varying carrier composition from 100 to 225 mg of CsNO_3 at 0 °C for 1 hour. The resulting CsClO_4 was subsequently measured for its "1"3"7Cs content at 661.8 keV. The result showed that the maximum recovery precipitation obtained was 83.87% at carrier addition of 225 mg. The optimum amount of two washing agents used during the process was also studied, where acetone and a mixture of ase tone and ethanol were used. The polarity of the washing agents was indicated by their dielectric constant (from 20 to 22.4). Analysis results indicate that the counts of "1"3"7Cs in the CsClO_4 after washing and the counts of the supernatant do not show significant difference. It is therefore concluded that polarity difference within those range have no significant effect on the solubility of CsClO_4. The precipitation of the irradiated U_3Si_2/Al at optimum condition results in "1"3"7Cs concentration of 0.011 μg/g sample or (4.415±0.035) x 10"2 μg/g for a 3 x 3 x 1.37 mm"3 irradiated U_3Si_2/Al sample. (author)