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Ratiko
Optimization of dry storage for spent fuel from g.a. siwabessy nuclear research reactor
Abstrak :
This study proposes a method of optimizing the dry storage design for nuclear-spent fuel from the G.A. Siwabessy research reactor at National Nuclear Energy Agency of Indonesia (BATAN). After several years in a spent fuel pool storage (wet storage), nuclear spent fuel is often moved to dry storage. Some advantages of dry storage compared with wet storage are that there is no generation of liquid waste, no need for a complex and expensive purification system, less corrosion concerns and that dry storage is easier to transport if in the future the storage needs to be sent to the another repository or to the final disposal. In both wet and dry storage, the decay heat of spent fuel must be cooled to a safe temperature to prevent cracking of the spent fuel cladding from where hazardous radioactive nuclides could be released and harm humans and the environment. Three optimization scenarios including the thermal safety single-objective, the economic single-objective and the multi-objective optimizations are obtained. The optimum values of temperature and cost for three optimization scenarios are 317.8K (44.7°C) and 11638.1 US$ for the optimized single-objective thermal safety method, 337.1K (64.0°C) and 6345.2 US$ for the optimized single-objective cost method and 325.1K (52.0°C) and 8037.4 US$ for the optimized multi-objective method, respectively.
Depok: Faculty of Engineering, Universitas Indonesia, 2018
UI-IJTECH 9:1 (2018)
Artikel Jurnal  Universitas Indonesia Library
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Pungky Ayu Artiani
Pemodelan dan simulasi tangki penyimpanan pada instalasi penyimpanan sementara bahan bakar nuklir bekas high temperature reactor 10 (HTR10) = Modeling and simulation of storage tank in interim storage for spent fuel of high temperature reactor 10( HTR 10)
Abstrak :
[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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Sri Ismarwanti
Studi eksperimental dan simulasi pengaruh initial pressure dan filling ratio pada unjuk kerja termal two-phase closed thermosyphon sebagai sistem pendingin pasif di kolam penyimpanan bahan bakar nuklir bekas = Experimental study and simulation of initial pressure and filling ratio effect on thermal performance two phase closed thermosyphon as passive cooling system in spent fuel storage pool / Sri Ismarwanti
Abstrak :
ABSTRAK
Pelajaran penting dari kecelakaan parah yang terjadi di pembangkit listrik tenaga nuklir Fukushima Daiichi Jepang menunjukkan bahwa panas sisa hasil peluruhan yang dibangkitkan dari bahan bakar nuklir bekas harus dapat didinginkan dengan baik. Dalam rangka menyerap panas sisa hasil peluruhan saat terjadi kecelakaan yang dipicu oleh kejadian station blackout, maka perlu dipertimbangkan penggunaan teknologi heat pipe tanpa wick (two-phase closed thermosyphon) dengan orientasi vertical sebagai sistem pendingin pasif di kolam penyimpanan bahan bakar nuklir bekas. Tujuan penelitian ini adalah untuk mengetahui karakteristik termal berupa pengaruh dari initial pressure, filling ratio, dan beban kalor pada unjuk kerjavertical two-phase closed thermosyphon yang akan digunakan sebagai sistem pendingin pasif di kolam penyimpanan bahan bakar nuklir bekas. Metode yang dilakukan dalam penelitian ini adalah dengan melakukan studi secara eksperimental dan simulasi menggunakan perangkat lunak RELAP5/MOD3.2. Vertical two-phase closed thermosyphon terbuat dari Cooper dengan geometri sebagai berikut: diameter dalam 0,1016 m, diameter luar 0,1031 m, dan panjang 6 m. Thermosyphon ini terdiri atas bagian evaporator, adiabatic dan condenser dengan rasio panjang yang sama. Air bebas mineral digunakan sebagai fluida kerja di dalamnya. Pembuangan kalor pada sisi condenser menggunakan air pendingin di dalam water jacket yang dipertahankan temperatur dan laju aliran volumetriknya. Dari eksperimen diperoleh hambatan termal terkecil sebesar 0,0151 C/W pada pengujian dengan filling ratio 80%, beban kalor 2500 W, temperatur air pendingin 26 C, laju aliran volumetrik pendingin 4 liter/menit, dan initial pressure -74 cm Hg. Hasil simulasi menunjukkan bahwa pemodelan yang dibangun dengan menggunakan perangkat lunak RELAP5/MOD3.2 menghasilkan distribusi temperatur yang hampir sama dengan eksperimen, sehingga dapat digunakan untuk simulasi selanjutnya dengan parameter yamg berbeda. Diharapkan hasil yang didapatkan dari eksperimen dan simulasi ini dapat menambah pengetahuan untuk mengetahui manajemen termal keselamatan nuklir bila terjadi station blackout.
ABSTRACT
The valuable lesson from a severe accident occurring in a nuclear power plant Fukushima Daiichi in Japan showed that the residual heat generated from the decay products of spent nuclear fuel must be cooled properly. The use of heat pipe technology without a wick (two-phase closed thermosyphon) with a vertical orientation as a passive cooling system in a spent fuel storage pool needs to be considered to absorb the decay heat during an accident triggered by station blackout.The purpose of this study was to determine the thermal characteristics such as the effect of the initial pressure, filling ratio, and the heat load on the performance of vertical two-phase closed thermosyphon to be used as a passive cooling system in a spent fuel storage pool. The method employed in this research were to conduct experimental and simulation studies using software RELAP5/MOD3.2. Vertical two-phase closed thermosyphon made of Copper with geometry as follows: an inside and outer diameter are 0.1016 m and 0.1031 m, respectively and 6 m long. Thermosyphon consists of the evaporator, adiabatic and condenser with the same length ratio. It uses demineralized water as the working fluid. Disposal of heat on the condenser side using cooling water in the water jacket that kept the temperature and volumetric flow rate. From the experiments showed that the smallest thermal resistance by 0.0151 ⁰C/W on testing by filling ratio of 80%, the heat load of 2500 W, cooling water temperature 26 ⁰C, the volumetric flow rate coolant4 liters/minute, and the initial pressure - 74 cm Hg. The simulation results show that the modeling software built using RELAP5 / MOD3.2 produce temperature distribution similar to the experiment. Expected results obtained from experiments and simulations can add knowledge to determine the thermal management of nuclear safety in station blackout
2016
T45938
UI - Tesis Membership  Universitas Indonesia Library
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Ainur Rosidi
Studi eksperimental penggunaan nano graphene sebagai fluida kerja vertical straight wickless-heat pipe = Experimental study use of graphene nano as a working fluid vertical straight wickless heat pipe
Abstrak :
Kolam penyimpan bahan bakar nuklir bekas saat ini masih menggunakan sistem pendingin aktif yang memiliki ketergantungan terhadap energi listrik. Kecelakaan parah di pembangkit listrik tenaga nuklir Fukushima Daiichi yang dipicu oleh kejadian station blackout menunjukkan gagalnya sistem pendingin aktif, sehingga penggunaan sistem pendingin pasif yang bekerja tanpa menggunakan pompa atau energi listrik menjadi suatu keharusan. Salah satu teknologi sistem pendingin pasif yang dapat diaplikasikan untuk mendinginkan panas hasil peluruhan dikolam penyimpan bahan bakar nuklir bekas adalah Vertical Straight Wickless-Heat Pipe dengan fluida kerja nano Graphene. Tujuan dari penelitian ini adalah untuk membandingkan karakteristik termal dan kinerja termal antara fluida kerja nano Graphene dan fluida kerja air demineral pada Vertical Straight Wickless-Heat Pipe dengan pengaruh dari filling ratio, laju alir pendingin volumetrik dan beban kalor. Metode yang dilakukan dalam penelitian ini adalah dengan melakukan studi secara eksperimental. Fluida nano Graphene dengan konsentrasi berat 1 digunakan sebagai fluida kerja. Dari hasil eksperimen hambatan termal terkecil diperoleh menggunakan fluida kerja nano Graphene sebesar 0,013 C/W pada pengujian dengan filling ratio 80 , beban kalor 2500 W dan laju aliran volumetrik pendingin 8 liter/menit.
Spent fuel storage pool is currently using an active cooling system that has a dependence on electrical energy. The severe accidents at the Fukushima Daiichi nuclear power plant triggered by station blackout show the failure of the active cooling system, so the use of a passive cooling system that works without the use of a pump or electrical energy becomes a necessity. One of the passive cooling system technologies that can be applied to cool the decay heat in a used nuclear fuel storage compound is the Heat Pipe with the Graphene nano working fluid. The purpose of this study was to compare the thermal and thermal performance characteristics between the Graphene nano working fluid and the demineralized water working fluid with the effect of filling ratio, volumetric coolant flow rate and heat load. The method used in this research is to conduct experimental. The simulation will be done to know the distribution of temperature in spent fuel storage pool which is filled with spent fuel. Nano fluid Graphene with a concentration of 1 is used as a working fluid. From the experimental results the smallest thermal resistance was obtained using a Graphene nanofluids of 0.013 C W on testing by filling ratio of 80 , the heat load of 2500 W and the volumetric flow rate coolant 8 liters minute.
Universitas Indonesia, 2017
T48479
UI - Tesis Membership  Universitas Indonesia Library
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Brilliand Tegar Verlambang
Studi eksperimental vertical two-phase closed thermosyphon sebagai pendingin pasif spent fuel storage pool di reaktor nuklir = Experimental study of vertical two phase closed thermosyphon as a passive cooling system in spent fuel storage pool nuclear reactor
Abstrak :
ABSTRAK
Penelitian ini bertujuan untuk mencari karakteristik termal dari Vertical Two Phase Closed Thermosyphon (VTPCT) yang berfungsi sebagai pendingin pasif Spent Fuel Storage Pool di reaktor nuklir. Metode yang digunakan dalam penelitian ini ialah eksperimental. Eksperimen yang dilakukan berfokus pada pencarian nilai resistansi termal dan performa terbaik dari VTPCT dengan beberapa variasi parameter uji. Parameter yang divariasikan adalah tekanan inisiasi, laju aliran air pendingin, dan beban kalor. Hasil yang didapat menunjukkan bahwa tekanan inisiasi -740 mmHg dan laju aliran pendingin 4 liter/menit akan menghasilkan resistansi termal dan performa terbaik pada beban kalor maksimal.
ABSTRACT
The objective of this research is to find the thermal characteristic of vertical two-phase closed thermosyphon as a passive cooling system in spent fuel storage pool nuclear reactor. The method that used in this research is experimental. The focus of the experiment is to investigate the influence of some parameters on VTPCT?s performance and thermal resistance. Parameters are varied in initial pressure, coolant flow rate, and heat input. Based on the experiment result, we can conclude that the performance and thermal resistance of VTPCT will reach the best value when the initial pressure and the coolant flow rate are -740 mmH and 4 liters/minutes.
2016
S63091
UI - Skripsi Membership  Universitas Indonesia Library