Recently, there has been increasing demand on finding new solid electrolytes based on glassy material, due to their potential applications for solid state rechargeable battery. Superionic conducting glasses have many advantageous compared with the crystalline, or composite electrolytes, such as easy in preparation, low melting point, no grain broundary, wide composition range and easy to be formed as thin film. Among superionic glasses, the family of silver phosphate glasses (AgI) x (AgPO 3 ) 1-x and lithium phosphate glasses (LiI) x (LiPO 3 ) 1-x , are the most interested materials to be investigated. Many experiments have been performed to investigate the properties of those materials. This paper will review the recent results of the lithium glasses (LiI) x (LiPO 3 ) 1-x , such as the preparation, appearance, structure, electrical and thermal properties. The x-ray data shows the precipitate occured at x=0.4, indicating the solubility limit of (LiI) x (LiPO 3 ) 1-x was reached at this composition. The microstructure data observed by SEM showed the different area between the smooth surface for x=0.3 and appearance of cluster at x=0.4. Comparison between glassy LiPO 3 and (LiI) 0.3 (LiPO 3 ) 1-x as the result of Raman spectra analysis, suggested a new feature at around 1000 cm -1 , indicating the depolymerization of the non bridging oxygen, due to the presence of LiI component. The room temperature conductivities of (LiI) x (LiPO 3 ) 1-x with x=0.3 and 0.4 are 2.7x10 -6 and 8.8x10 -7 S/cm, respectively, which are 3 orders of magnitudes higher than the undoped glass LiPO 3 . In general, the silver glass has better ionic conductivity than the lithium glass; but in application the lithium battery has better performance and produces higher voltage.
During the operation of the research reactor RSG-GAS, there are many design parameters should be verified based on postulated accidents. Several design basis accidents (DBA) such as loss of flow accident (LOFA) and reactivity-initiated accident (RIA) also have been conducted separately. This paper discusses about possibility of simultaneous accidents of LOFA and RIA. The accident analyses carry out calculation for transient condition during RIA, LOFA, and postulated accident of simultaneous LOFA-RIA. This study aims to conduct a safety analysis on simultaneous LOFA and RIA, and investigate the impact on safety margins. The calculations are conducted by using the PARET code. The maximum temperature of the center fuel meat at nominal power of 30 MW and steady state conditions is 126.10°C and MDNBR of 2.94. At transients condition, the maximum center fuel meat temperature for LOFA, RIA and simultaneous LOFA-RIA are consecutively 132.99°C, 135.67°C and 138.21°C, and the time of reactor trip are 3.2593s, 3.6494s and 2.7118s, respectively. While the MDNBR for LOFA, RIA and simultaneous LOFA-RIA are respectively at transient condition are 2.88, 2.58 and 2.63, respectively. It is shown that, simultaneous LOFA-RIA has the fastest trip time. In this case, the low flow trip occurs first in advance to over power trip. From these results, it can be concluded that the RSG-GAS has adequate safety margin against transient of simultaneous LOFA-RIA.Keywords: RSG-GAS, Simultaneous, LOFA, RIA, PARET
Currently, Indonesia through BATAN is operating three research reactors, namely the RSG-GAS reactor with the power of 30 MWt at Puspiptek south Tangerang (the first criticality in 1987), the TRIGA 2000 reactor with the power of 2 MW in Bandung which the first criticality in 1965 with the power of 250 kW, was increased to 1 MW in 1971, and further upgraded to 2 MW in 2000. Beside that, there is Kartini reactor with a power of 100 kW located in Yogyakarta (first criticality in 1979). These reactors are quite old, and in accordance with Bapeten regulations, have carried out the first periodic safety review, to obtain a reactor license for the next 10 years of operation. In line with this, one of BATAN's current national research programs is to increase the production of radioisotopes and radiopharmaceuticals, where reactors play a very important role in the production of certain isotopes. In tracing the data obtained from operational reports related to irradiation requests from reactor users, namely PTRR, PSTNT, and PT INUKI for radioisotope production, which has been carried out in the last 5 years, May 2015 until 25 August 2020, show that the irradiation request at RSG-GAS is still not optimal. In term of the utilization of RSG-GAS, it can still be optimized, which in this case needs to be balanced with post-irradiation processing capabilities. Meanwhile, from the results of tracing and data collection, it can be shown that at this time the reactors are still operating. The utilization activities of the reactors complement each other according to their age and facilities.
ABSTRAK DISTRIBUSI UNSUR MAKRO DAN MIKRO DALAM ABU GUNUNG MERAPI YOGYAKARTA. Telah dilakukan analisis kandungan unsur dalam abu Gunung Merapi pasca erupsi Oktober-Nopember 2010 dengan teknik analisis aktivasi neutron (AAN). Pengambilan sampling dilakukan oleh peneliti PTAPB-BATAN pada tanggal 9 dan 10 Nopember 2010 di 10 titik sampling. Lokasi sampling sebanyak 4 titik di Kabupaten Sleman, 1 titik di Kabupaten Magelang, 3 titik di Kabupaten Klaten dan 2 titik di Kabupaten Boyolali. Sampel abu vulkanik dikeringkan,diayak lolos saring 200 mesh dan ditimbang 30-50 mg dalam vial polietilen. Iradiasi dilakukan pada fluks neutron termal 1013 n.cm-2.det-1 di fasilitas iradiasi Reaktor Serba Guna GA. Siwabessy, Serpong. Pencacahan cuplikan pasca iradiasi dilakukan dengan detektor resolusi tinggi HPGe yang digabungkan dengan penganalisis puncak multi saluran. Analisis data dilakukan dengan perangkat lunak GENIE 2000 dan k0-IAEA. Hasil analisis menunjukkan bahwa unsur dalam abu vulkanik terdiri atas unsur makro (dalam persen) Al 10,
NEUTRONIC AND THERMAL HYDRAULICS ANALYSIS OF CONTROL ROD EFFECT ON THE OPERATION SAFETY OF TRIGA 2000 REACTOR.Analysis of neutronic and thermal-hydraulics parameters of whole operation cycle is very important for the safety of reactor operation. During the reactor operation cycle, the position of the control rods will change due to reactivity changes. The purpose of this study is to determine the effect of control rods position on neutronic and thermal-hydraulics parameters in relation to the safety of reactor operation of the TRIGA 2000 reactor using silicide fuel of MTR plate type. Those parameters are power peaking factor, reactivity coefficients, and steady-state thermohydraulic parameters. Neutronic calculations are performed using a combination of WIMSD/5 and Batan-3DIFF codes and for thermal-hydraulics the calculations are done using WIMSD/5 and MTRDYN codes. The calculation results show that the reactivity coefficient values are negative for all control rod positions both at CZP and HFP conditions. The MTC value decreases when the control rod is inserted into the active core while the FTC value increases. The total ppf results and temperature in steady-state rise when the control rods are inserted of into the active core whereby the maximum value occurs at the position of the control rods of 20 cm from the bottom of the active core. The calculation results of ppf, reactivity coefficient, and thermal-hydraulics parameters lay below safety limits, indicating that the TRIGA 2000 reactor can safely use U 3 Si 2 -Al silicide fuel as a substitute fuel for cylindrical type fuel. ABSTRAK ANALISIS NEUTRONIK DAN TERMOHIDRAULIK PENGARUH POSISI BATANG KENDALI TERHADAP KESELAMATAN OPERASI REAKTOR TRIGA 2000. Analisis parameterneutronikdan termohidraulik dari seluruh siklus operasi sangat penting untuk keselamatan operasi reaktor. Selama siklus operasi reaktor, posisi batang kendali akan berubah karena perubahan reaktivitas. Tujuan dari penelitian ini adalah untuk mengetahui pengaruh posisi batang kendali terhadap parameter neutronik dan termohidraulik terkait keselamatan operasi reaktor TRIGA 2000 menggunakan bahan bakar silisida jenis MTR. Parameter yang ditentukan adalah faktor puncak daya, koefisien reaktivitas, dan parameter termohidraulika pada keadaan tunak. Perhitungan neutronikl dilakukan menggunakan kombinasi program WIMSD/5 dan Batan-3DIFF dan untuk termohidraulik dilakukan menggunakan program WIMSD/5 dan MTRDYN. Hasil perhitungan menunjukkan bahwa nilai koefisien reaktivitas negatif untuk semua posisi batang kendali baik pada kondisi CZP dan HFP. Nilai MTC berkurang ketika batang kendali dimasukkan ke teras aktif sementara nilai FTC meningkat. Hasil ppf total dan parameter dalam kondisi tunak meningkat dengan memasukkan batang kendali ke dalam teras aktif dimana nilai maksimum terjadi pada posisi batang kendali 20 cm dari bagian bawah teras aktif. Hasil perhitungan ppf, koefisien reaktivitas dan parameter termohidraulik berada di bawah batas keselamatan, ini menunjukkan bahwa reaktor TRIGA 2000 dapat menggu...
The operation cycle of the RSG-GAS reactor is regulated by control rod positions from the lowest to uppest positions. It is of necessary to know the effect of this control rods positions to the safety operation parameter a long the cycle. The objective of this research is to confince that the changes of safety operation parameter still meet the its safety limits. The neutronics and thermalhydraulics parameter to be observed are power peaking factor, kinetic and steady state parameters. Calculations are conducted by a combination code of WIMSD/5 and MTRDYN. The main results of maximum axial power peaking factor is 1.84 at control rod position of 20 cm. The maximum temperature of cooling, cladding and fuel are consecutively 67.18 °C, 122.26 °C, and 123.24 °C. These results lay far under safety limits of maximum temperature of coolant and fuel of 100 °C dan 200 °C at steady state operation of the RSG-GAS reactor which means that the reactor operation is safe as long as the cicle operation.
The Indonesian Multipurpose Reactor, RSG-GAS reactor will accomplish its first lifetime in December 2020. The reactor has been operated in safe and reliable manner for about 33 years since it commenced in operation in 1987 to serve radioisotopes production, NAA, neutron beam experiments, material irradiation, and reactor physics experimental activities as well as training. The paper is intended to evaluate its in-core fuel management that is the conformance between the theory and implementation of the equilibrium core. Evaluation of the reactor operation parameter was carried out for core numbers 91 – 100. The data show that excess reactivity, shutdown reactivity and control rod reactivity have no significant difference at each core. The result shows that the BATAN-FUEL accurately determine the equilibrium core and its fuel loading pattern.This in-core fuel management of the RSG-GAS reactor supports the safety of reactor operation.
Keselamatan merupakan faktor utama dan pertama dalam pengoperasian suatu fasilitas atau instalasi, apalagi dalam pengoperasian reaktor nuklir yangmengandung potensi bahaya radioaktif. Buku ini membahas secara garis besar tentang keselamatan reaktor nuklir terutama prinsip-prinsip keselamatan reaktor dan persyaratan sistem keselamatan suatu reaktor nuklir. Agar dapat memberi gambaran yang jelas tentang apa, bagaimana dan seberapa tinggi keselamatan reaktor nuklir, salah satu reaktor nuklir yaitu reaktor RSG-GAS, di Kawasan Nuklir Serpong, dipilih sebagai obyek penerapan prinsip dan persyaratan keselamatan tersebut diatas. Bagian awal adalah mengenalkan reaktor nuklir, terutama mengenai bagian utama reaktor, prinsip kerja dan manfaat dan resiko bahayanya. Kemudian disajikan prinsip keselamatan reaktor nuklir meliputi filsofi, tujuan dan kriteria keselamatan, termasuk prisip pertahanan berlapis secara rinci, analisis keselamatan dan tingkat kecelakaan nuklir. Pembahasan selanjutnya adalah persyaratan sistem keselamatan reaktor nuklir. Akhirnya disajikan penerapan prinsip keselamatan reaktor pada reaktor RSG-GAS meliputi deskripsi reaktor, jenis–jenis kecelakaan kecelakaan dasar desain, dan secara rinci tentang sistem pertahanan berlapis dan sistem keselamatan reaktor. Sebagai penutup adalah uraian tentang pengalaman pengoperasian reaktor RSG-GAS selama 28 tahun mulai tahun 1987 dan saran untuk mempertahankan tingkat keselamatan reaktor untuk operasi selanjutnya.
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