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Pungky Ayu Artiani
"[ABSTRAK
Limbah Bahan Bakar Nuklir Bekas (BBNB) merupakan salah satu limbah yang dihasilkan dalam pengoperasian reaktor nuklir. Limbah ini masih menghasilkan produk fisi dan panas hasil reaksi yang masih tinggi sehingga perlu dikelola dengan baik agar efek radiasi yang ditimbulkan tidak keluar di lingkungan. Penelitian ini akan dilakukan pemodelan panas peluruhan pada penyimpanan kering BBNB bentuk pebble dengan tipe storage tank yang telah digunakan pada reaktor HTR 10 menggunakan software ORIGEN-ARP. Dengan computational fluid dynamics (CFD) menggunakan Comsol Multiphysics maka pengaruh kecepatan udara pendingin dan ketebalan lapisan pengungkung terhadap profil suhu di setiap segmen storage dapat diketahui sehingga keselamatan penyimpanan BBNB pada aspek suhu dapat dianalisis. Dari hasil perhitungan dapat diketahui bahwa panas peluruhan yang dihasilkan oleh BBNB setelah keluar dari reaktor sebesar 620,2260 watt. Panas peluruhan tersebut semakin menurun seiring dengan lamanya waktu penyimpanan. Ketebalan beton tidak terlalu berpengaruh terhadap penurunan suhu di storage tank. Hal ini disebabkan oleh konduktivitas panas beton yang rendah sehingga laju perpindahan panas di setiap variasi ketebalan tidak berbeda secara signifikan. Ketebalan stainless steel berpengaruh terhadap gradien perubahan suhu pada storage tank. Semakin tipis stainless steel maka semakin banyak laju panas yang dialirkan dari grafit ke beton, sehingga suhu pada beton semakin besar. Semua hasil simulasi pada berbagai kondisi memenuhi syarat parameter suhu maksimum keselamatan.

ABSTRACT
Nuclear Fuel Waste is one of waste generated in operation of nuclear reactors. This waste is still producing fission products and heat of reaction that need to be managed properly so the effects of radiation emitted do not expose to environment. This research will be carried out modeling the decay heat in dry storage of pebble nuclear spent fuel with the type of storage tanks that have been used in the reactor HTR 10 using ORIGEN-ARP software. The effects of cooling air velocity and confinement layer thickness on temperature profile in every segment of storage can be determined with computational fluid dynamics (CFD) using Comsol Multiphysics so the safety of nuclear spent fuel storage on temperature aspects can be analyzed. Based on the calculation results can be seen that the decay heat generated by nuclear spent fuel after coming out from the reactor is 620.2260 watts. The decay heat decreases as the length of storage time. Concrete thickness does not significantly affect the declining temperature gradient in the storage tank. This is caused by the low thermal conductivity of concrete so the heat transfer rate in each variation of thickness is not different significantly. Stainless steel thickness affects the declining temperature gradient. Thinner the thickness of the stainless steel is used, greater the reduction of temperature gradient so equilibrium temperature of storage tank can be quickly achieved. All simulation results under various conditions compliy with the maximum temperature parameters of safety.;Nuclear Fuel Waste is one of waste generated in operation of nuclear reactors. This waste is still producing fission products and heat of reaction that need to be managed properly so the effects of radiation emitted do not expose to environment. This research will be carried out modeling the decay heat in dry storage of pebble nuclear spent fuel with the type of storage tanks that have been used in the reactor HTR 10 using ORIGEN-ARP software. The effects of cooling air velocity and confinement layer thickness on temperature profile in every segment of storage can be determined with computational fluid dynamics (CFD) using Comsol Multiphysics so the safety of nuclear spent fuel storage on temperature aspects can be analyzed. Based on the calculation results can be seen that the decay heat generated by nuclear spent fuel after coming out from the reactor is 620.2260 watts. The decay heat decreases as the length of storage time. Concrete thickness does not significantly affect the declining temperature gradient in the storage tank. This is caused by the low thermal conductivity of concrete so the heat transfer rate in each variation of thickness is not different significantly. Stainless steel thickness affects the declining temperature gradient. Thinner the thickness of the stainless steel is used, greater the reduction of temperature gradient so equilibrium temperature of storage tank can be quickly achieved. All simulation results under various conditions compliy with the maximum temperature parameters of safety., Nuclear Fuel Waste is one of waste generated in operation of nuclear reactors. This waste is still producing fission products and heat of reaction that need to be managed properly so the effects of radiation emitted do not expose to environment. This research will be carried out modeling the decay heat in dry storage of pebble nuclear spent fuel with the type of storage tanks that have been used in the reactor HTR 10 using ORIGEN-ARP software. The effects of cooling air velocity and confinement layer thickness on temperature profile in every segment of storage can be determined with computational fluid dynamics (CFD) using Comsol Multiphysics so the safety of nuclear spent fuel storage on temperature aspects can be analyzed. Based on the calculation results can be seen that the decay heat generated by nuclear spent fuel after coming out from the reactor is 620.2260 watts. The decay heat decreases as the length of storage time. Concrete thickness does not significantly affect the declining temperature gradient in the storage tank. This is caused by the low thermal conductivity of concrete so the heat transfer rate in each variation of thickness is not different significantly. Stainless steel thickness affects the declining temperature gradient. Thinner the thickness of the stainless steel is used, greater the reduction of temperature gradient so equilibrium temperature of storage tank can be quickly achieved. All simulation results under various conditions compliy with the maximum temperature parameters of safety.]"
2016
T45267
UI - Tesis Membership  Universitas Indonesia Library
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Arifin Istavara
"Penelitian ini bertujuan untuk memberikan solusi penyimpanan Bahan Bakar Nuklir Bekas (SNF) di Indonesia. Karena keterbatasan ruang pada penyimpanan tipe basah, maka penelitian ini merancang, mensimulasikan, melakukan eksperimen, dan menghitung biaya pembuatan penyimpanan dry cask storage secara simultan. Dalam studi ini, desain dry cask storage dioptimalkan dengan menggunakan dua objective functions secara bersamaan yaitu fungsi keselamatan (yang menggabungkan parameter kekritisan, proteksi radiasi dan penghilangan panas) dan fungsi biaya. Perhitungan optimasi kemudian divalidasi dan dianalisis dengan data eksperimen dari prototipe dry cask storage. Dengan menentukan decision variables dan constraints, kemudian memasukkannya ke dalam Matlab software, diperoleh tiga pilihan hasil optimasi, safety optimized, cost optimized dan multi-objective optimized. Dalam multi-objective optimized, desain penyimpanan kering yang optimal diperoleh untuk radius luar beton dan timbal (Pb) masing-masing sebesar 0,06 m dan 0,51 m. tinggi ventilasi dan lebar masing-masing sebesar 0,15 m dan 0,5 m, dan perbedaan ketinggian ventilasi sebesar 2,43 m. Untuk kelima variabel diatas, nilai optimum temperatur permukaan kanister adalah 66,8 °C dan biaya yang dibutuhkan untuk pembuatan dry cask storage adalah $147,827. Ketebalan material yang dibutuhkan didapatkan nilai yang paling optimum untuk Pb 0,06 m dan beton 0,51 m, dari validasi menggunakan MicroShield software didapatkan paparan permukaan penyimpanan dry cask sebesar 104,8 mR/jam sehingga masih dalam batas aman dari nilai maksimum yang ditentukan yaitu 160 mR/jam. Demikian pula dari simulasi suhu permukaan tabung menggunakan Ansys Fluent software untuk kelima variabel di atas, nilai suhu permukaan mendekati perhitungan yang persamaannya dimasukkan ke dalam Matlab software. Validasi menggunakan data eksperimen dari prototipe dry cask storage dan juga perhitungan manual diperoleh nilai temperatur yang juga relatif mendekati hasil optimasi, yaitu 45,2 °C untuk temperatur dari eksperimen dan 50.2 °C untuk temperatur perhitungan teori. Hasil nilai optimasi terpilih dengan tetap menjaga keamanan termal menunjukkan bahwa acuan dalam pembuatan desain dengan skala 1:1 dapat menggunakan estimasi untuk keamanan termal T1, untuk jenis SNF Materials Testing Reactor (MTR) dengan umur setelah sepuluh tahun disimpan pada jenis penyimpanan tipe basah.
......This research aims to provide a solution for Indonesia's spent nuclear fuel (SNF) storage. Due to the limited storage space in wet type storage, this research designs, simulates, conducts experiments, and calculates the cost of making dry cask storage simultaneously. In this study, the dry storage design was optimized by using two objective functions simultaneously: safety function (which combines criticality parameters, radiation protection and heat removal) and cost function. The optimization calculations were then validated and analyzed with experimental data from the dry cask storage prototype. By determining the decision variables and constraints and then inputting them into the Matlab software, three choices of optimization results are obtained, safety optimized, cost optimized and multi-objective optimized. In multi-objective optimized, the optimum dry storage design is obtained for the concrete outer- and lead (Pb) outer-radius of 0.06 m and 0.51 m respectively. vent-height, -widt by 0.15 m and 0.5 m respectively, and a vent elevation difference of 2.43 m. For the five variables above, the optimum value for the canister surface temperature is 66.8 °C and the cost required to make dry storage is $ 147,827.The required thickness of the material obtained the most optimum value for Pb 0.06 m and concrete 0.51 m, from validation using MicroShield software, it was obtained that the dry cask storage surface exposure was 104.8 mR/h so that it is still within the safe limit of the maximum value specified, which is 160 mR/h. Similarly, from the simulation of canister surface temperature using Ansys Fluent for the five variables above, the surface temperature value is close to the calculation whose equations are inputted into matlab. Validation using experimental data from the dry storage prototype and also manual calculations obtained temperature values which are also relatively close to the optimization results, 45.2 °C for temperature from experiments and 50.2 °C for temperature from manual calculations. The result of the selected optimization value while maintaining thermal safety indicates that reference in making designs with a scale of 1:1 can use the estimate for the thermal safety of T1, for the type of SNF Materials Testing Reactor with age after ten years stored in the wet storage type."
Depok: Fakultas Teknik Universitas Indonesia, 2022
T-pdf
UI - Tesis Membership  Universitas Indonesia Library
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Benjamin, M.
New York : Van Nostrand Reinhold, 1983
621.483 3 BEN n
Buku Teks  Universitas Indonesia Library