Badan Tenaga Nuklir Nasional: Jurnal BATAN
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PENENTUAN TINGKAT KLIERENS LIMBAH RADIOAKTIF HASIL SEMENTASI KONSENTRAT EVAPORASI DAN TINJAUAN KESELAMATAN PEMBUANGANNYA
Full text linkTelah dilakukan penelitian untuk mengukur tingkat klierens 14 unit shell beton 950 L milik Instalasi Pengelolaan Limbah Radioaktif, Direktorat Pengelolaan Fasilitas Ketenaganukliran, Badan Riset dan Inovasi Nasional (IPLR-DPFK BRIN). Shell-shell beton tersebut merupakan paket hasil olahan konsentrat evaporasi limbah radioaktif cair yang dikondisioning dengan teknik sementasi. Jika telah memenuhi tingkat klierens, maka shell-shell beton tersebut dapat dibebaskan dari pengawasan Badan Pengawas Tenaga Nuklir (BAPETEN) melalui mekanisme klierens sehingga pada akhirnya dapat menambah ruang kosong di gedung penyimpanan sementara limbah radioaktif. Penelitian dilakukan dengan mengukur laju dosis radiasi, tingkat kontaminasi permukaan, dan konsentrasi aktivitas radionuklida pemancar α, β, dan ϒ untuk menentukan tingkat klierens. Dari penelitian yang telah dilakukan dapat diketahui bahwa laju dosis tertinggi 0,15 µSv/jam, tingkat kontaminasi permukaan tertinggi sebesar 0,0148 Bq/cm2 untuk radionuklida pemancar α dan 0,0935 Bq/cm2 untuk radionuklida pemancar β. Nilai tingkat klierens radioaktivitas unit shell beton 950 L yang diuji berkisar antara 0,47020 – 0,66730. Mengacu pada Peraturan Kepala BAPETEN Nomor 16/2012 tentang Tingkat Klierens, kandungan radionuklida dalam shell-shell beton 950 L yang diuji telah mencapai tingkat klierens. Pembuangan klierens terhadap 14 unit shell beton tersebut sangat mungkin untuk dilakukan karena shell-shell beton tersebut tidak mengandung bahan berbahaya dan beracun (B3). Perkiraan dosis radiasi yang akan diterima oleh kelompok kritis, tidak akan melebihi 10 µSv per tahun.
SINTESIS PADUAN BARU BAJA OXIDE DISPERSION STRENGTHENED (ODS) FERITIK Fe-Cr-Al-W-Ti-Zr DENGAN DISPERSOID Y2O3 SEBAGAI KANDIDAT MATERIAL CLADDING ELEMEN BAKAR REAKTOR NUKLIR DENGAN METODE MEKANOSINTESIS
Full text linkBahan struktur merupakan salah satu kunci penting dalam penelitian reaktor nuklir generasi keempat. Sejak peristiwa kecelakaan di pembangkit listrik tenaga nuklir Fukushima–Daiichi, telah terjadi peningkatan pengembangan Accident Tolerant Fuel (ATF) Cladding atau kelongsong bahan bakar toleran kecelakaan untuk menghindari kecelakaan reaktor air ringan. Maka dari itu Inovasi perekayasaan ATF merupakan salah satu kegiatan dalam litbang material maju yang sedang banyak dikembangkan. Kandidat material yang paling menjanjikan untuk ATF cladding adalah Baja yang diperkuat dengan dispersi oksida (ODS). Dalam penelitian ini baja ODS feritik Fe-Cr-Al-W-Ti-Zr-Y2O3 disintesis dengan metode mekanosintesis menggunakan alat planetary ball mill (PBM) dengan variasi komposisi Zr sebesar 0%, 0.5%, 1%, dan 1.5%. Mekanosintesis dilakukan selama 8 jam dengan menggunakan bola stainless steel. Perbandingan berat antara sampel dengan bola adalah 1:10. Kemudian dilakukan karakterisasi menggunakan mikroskop optik, XRD, dan SEM-EDS. Hasil observasi menunjukkan homogenitas yang baik pada bahan hasil sintesis
Experimental Study of The Influences of Inclination Angle and Heat Load on Loop Heat Pipe Thermal Performance
Full text linkThe utilization of nuclear power brings out a lot of benefits in fulfilling human power needs, however, the thermal incident caused by the failure of an active cooling system because of an earthquake followed by the tsunami such as on the Nuclear Power Plant at Fukushima Dai-Ichi Japan could be taken for lesson learn to keep improve nuclear installation operation safety aspects. Loop heat pipe (LHP) as an alternative cooling system technology could be utilized to handle thermal problems on nuclear installations. This research aims to know the influence of the inclination angle and heat load on the LHP thermal performance. The experimental investigation was performed with varying the inclination angle of 0°, 2.5°, and 5°, and heat load given at 60°C, 70°C, 80°C, and 90°C. LHP was used demineralized water working fluid with a 100% filling ratio. LHP was vacuumed on 2.666,4 Pa. The cooling air velocity in the condenser given by 2,5 m/s. The result of this experiment showed that LHP has the best thermal performance with the lowest thermal resistance of 0.0043°C/W. This result was obtained when the LHP operated with a 5° inclination angle and hot water as the heat load of 90°C. The conclusion from this research is showing better LHP thermal performance as the inclination angle increase on LHP because the steam speed that formed bigger, and condensate flows back to the evaporator faste
Cover and Table of Content
No full textCover and Table of Content for Eksplorium Volume 45 No. 1 May 2024 Edition
Phytoremediation of Hexavalent Chromium Using Aquatic Plants in Nickel Mine Waste
Full text linkThe abundant wealth that Indonesia has is very profitable. Wealth is not only from natural resources, but wealth or biodiversity is also able to make Indonesia an independent country in managing its environment. One of the varieties that can be utilized is the existence of aquatic plants that can be used in the restoration of polluted environments. The ability of plants to recover from pollutants is called phytoremediation. Hexavalent chromium/ Cr(IV) is a hazardous waste originating from the washing of ore/open pit waste from rainwater washing. The quality standard allowed for Cr (IV), according to the Minister of Environment Regulation No. 9 of 2006, concerning the Quality Standard of Wastewater for Nickel Ore Mining Businesses and/or Activities is 0.1 mg/L. Besides being used to reduce pollutant loads, this aquatic plant can also provide aesthetic value because it has a very beautiful shape, type, color, and flowers. The purpose of this research is to find out which plants can be used to reduce hexavalent chromium levels. Variations of aquatic plants that can reduce levels of hexavalent chromium which are harmful to living things include water hyacinth/Eichornia crassipes; water hyacinth; Kayambang/ Salvinia Cucullata; Kiambang/ Apu Wood/ Pistia Stratiotes; Hydrilla verticillata; Water Bamboo/Equisetum hyemale; Water spinach / Ipomoea Aquatica; and Sagittaria lancifolia. This aquatic plant can reduce Cr (IV) up to 99.5%. The ability of these aquatic plants not only to reduce Cr (IV) but also to reduce TSS, BOD, and COD and to neutralize pH. The combination of several aquatic plants also provides a high effectiveness value
MODEL SIMULATION OF THE EFFECT OF ZINC PHOSPHATE INHIBITOR ON CORROSION RATE OF SECONDARY COOLING PIPE FOR PRESSURIZED WATER REACTOR USING PREDICTOR-CORRECTOR METHOD
Full text linkCorrosion is one of the unavoidable problems in nuclear reactor cooling systems. Secondary Cooling Pipe Multi-Purpose Reactor G.A Siwabessy (MPR-GAS) based on low carbon steel is very easy to oxidize because it is an open circulation cooling system. Zinc-phosphate inhibitor (ZnPO4) is one of the inhibitors used to inhibit the corrosion reaction that occurs between the low carbon steel cooling pipe and the cooling water environment. The research has been carried out on numerical calculations to find a solution for the corrosion rate model of steel with and without an inhibitor by the Predictor-corrector method. The simulation results show that the effect of ZnPO4 inhibitor on the corrosion rate of steel is seen as a relationship between inhibitor concentration and stable time, if the inhibitor concentration increases, the stable time will also increase. The rate of corrosion that occurs (reducing the concentration of corroded product). Therefore, the recommended inhibitor concentration value is 0.9% for models in 0.1 M HCL medium. This concentration is the most appropriate concentration to slow down the corrosion rate. most minimal
Analytical Method Validation of Thorium in Ore Sample Using UV-Vis Spectrophotometer
Full text linkMonazite contains several rare earth elements (REE) along with radioactive elements, i.e., thorium (Th) and uranium (U). Thorium content in monazite is several times higher than uranium. Monazite contains around 12% thorium oxide, but the thorium content in this mineral varies depending on location. To determine the thorium content in monazite, an appropriate and validated analytical method is needed so that the reliability of the test results can be trusted. Apart from that, method validation is one of the clauses in SNI ISO/IEC 17025:2017 that must be fulfilled by the laboratory to be certified and produce reliable data. This research aims to validate analytical methods for non-standard and modified methods that are likely to be used outside the scope. In this research, the method used to digest and analyze thorium in mineral samples refers to the ASTM E2941-14 method with several modifications. Therefore, the analysis method needs to be validated. Validation of the analytical method is carried out by testing several parameters such as linearity and working range tests, accuracy, precision (repeatability), Limit of Detection (LOD), and Limit of Quantitation (LOQ). The results of linearity, accuracy, and repeatability tests that meet the acceptance requirements can be used as a method of validation evaluation. The results of the method validation parameter test met the acceptance requirements, with the linearity test showing a coefficient of determination (R2) of 0.997, the accuracy test showing % a recovery value of 106.22%, and the precision (repeatability) test showing %RSD of 3.76% with LOD value is 0.650 mg/L, and LOQ is 0.724 mg/L. Based on the results of these parameter tests, the method for analyzing thorium in mineral samples was validated
Analysis of the Reactivity Coefficient of the PWR Thorium Fuel
Full text linkIn design, control, and safety—especially in PWR reactors—the Reactivity Coefficient parameter is crucial. The validation of every new library for an accurate parameter prediction is then crucial. The purpose of this work is to determine the value of the reactivity coefficient at BOC and EOC using the WIMDS code based on ENDF/B-VIII.0 nuclear data files. The PWR-1175 MWe experiment critical reactors, which use Th-UO2 (thorium) fuel pellets, are a set of light water-moderated lattice experiments that are used for this purpose. The study is applied to the new cross-section libraries for WIMSD-5B and WIMSD-5B with ENDF/B-VIII.0 lattice code. The results showed that the fuel temperature reactivity coefficients for the PWR reactor at BOC and EOC using new libraries are – 4.07 pcm/K and – 2.72 pcm/K, respectively. Moderator Temperature Reactivity Coefficient at BOC and EOC are -1.8E-03 pcm/K and 3.73 pcm/K, respectively. Compared to the experimental data of the reactor core, the difference is in the range of 5.0 %. It can be concluded that for the PWR using thorium fuel as a model, all reactivity coefficients are negative and it is a good design for the safety of operation
PENENTUAN KEMURNIAN RADIONUKLIDA DARI PRODUK GENERATOR Mo-99/Tc-99m NON-FISI MENGGUNAKAN SPEKTROMETER GAMMA
Full text linkRadionuklida medis teknesium-99m (Tc-99m) adalah jenis radionuklida yang paling banyak pemanfaatannya pada proses diagnostik di dalam dunia kedokteran nuklir. Hal ini berkaitan dengan karakteristiknya yang memiliki masa paruh selama 6 jam dengan melepaskan energi gamma tunggal (Eγ) sebesar 140 keV. Tc-99m adalah produk dari generator Mo-99/Tc-99m dan merupakan anak luruh dari molibdenum-99 (Mo-99) yang memiliki masa paruh selama 66 jam. Radionuklida Mo-99 dapat diproduksi melalui reaksi aktivasi neutron yang membutuhkan target alam non fisi molibdenum trioksida (MoO3) sebagai target di reaktor nuklir, sehingga disebut generator Mo-99/Tc-99m non fisi. Tujuan penelitian ini yaitu dapat menentukan nilai kemurnian produk Tc-99m dari generator Mo-99/Tc-99m non fisi menggunakan metode spektrometer gamma. Hal ini dilakukan dengan menganalisis kalibrasi energi dan efisiensi pada spektrometer gamma dengan menggunakan sumber standar cair (Liquid Source) campuran Ba-133 dan Eu-152, dan sumber standar titik (Point Source) Eu-152, sesuai geometri masing-masing untuk pengukuran lolosan Mo-99 dan produk Tc-99m yang dihasilkan secara berurutan untuk setiap proses elusi tiga generator. Proses aktivasi neutron dari molibdenum alam (MoO3) dilakukan di reaktor nuklir G.A. Siwabessy, Indonesia. Kemurnian radionuklida produk Tc-99m dari generator Mo-99/Tc-99m non fisi diperoleh sebesar 99,999% untuk setiap elusi sedangkan lolosan Mo-99 terbesar yaitu 0,0018 dan terendah yaitu 1,04 x 10-4 µCi Mo-99/mCi Tc-99m. Hasil kelolosan Mo-99 yang diperoleh berada dibawah nilai 0,15 µCi Mo-99/mCi Tc-99m yang ditetapkan oleh US Pharmacopoeia, sehingga produk Tc-99m yang dihasilkan baik, dan menunjukan bahwa produk tersebut dapat digunakan untuk proses pelabelan menjadi radiofarmaka. Metode pengukuran kemurnian radionuklida ini dapat digunakan sebagai penentuan parameter kendali kualitas produk generator Mo-99/Tc-99m non fisi
Cover and Table of Content
No full textCover and Table of Content for Eksplorium Volume 44 No. 2 November 2023 Edition