55 research outputs found
Effect Of U-9mo/Al Fuel Densities On Neutronic And Steady State Thermal Hydraulic Parameters Of Mtr Type Research Reactor
Get PDFThe objectives of this research work are to carry out a detailed neutronic and steady state thermal hydraulics analysis for a MTR research reactor fuelled with the low enrichment U-9Mo/Al dispersion fuels of various uranium densities. The high density uranium fuel will increase the cycle length of the reactor operation and the heat flux in the reactor core. The increasing heat flux at the fuel will causing increase the temperature of the fuel and cladding so that the coolant velocity has to be increased. However, the coolant velocity in the fuel element has a limit value due to the thermal hydraulic stability considerations in the core. Therefore, the neutronic and the steady state thermal hydraulic analysis are important in the design and operation of nuclear reactor safety. The calculations were performed using WIMS-D5 and MTRDYN codes. The WIMS-D5 code used for generating the group constants of all core materials as well as the neutronic and steady state thermal hydraulic parameters were determined by using the MTRDYN code. The calculation results showed that the excess reactivity increases as the uranium density increases since the mass of fuel in the reactor core is increased. Using the critical velocity concept, the maximum coolant velocity at fuel channel is 11.497 m/s. The maximum temperatures of the coolant, cladding and fuel meat with the uranium density of 3,66 g/cc are 70.85°C, 150.79°C and 153.24°C, respectively. The maximum temperatures are fulfilled the design limit so reactor has a safe operation at the nominal power
PENGARUH LITERASI KEUANGAN, TEKNOLOGI INFORMASI, DAN ETIKA BISNIS ISLAM TERHADAP PENDAPATAN PELAKU USAHA MIKRO DI KECAMATAN GEDUNG SURIAN DAN KEBUN TEBU
No full textABSTRAK
Indonesia merupakan Negara berkembang yang masih
melaksanakan usaha-usaha pembangunan. Salah satu pembangunan yang
sedang dijalankan di Indonesia saat ini adalah pembangunan ekonomi.
Pembangunan ekonomi mengarah pada kesempatan kerja dan
pertumbuhan ekonomi yang berkelanjutan. Tujuan dalam penelitian ini
adalah untuk mengetahui pengaruh literasi keuangan terhadap
pendapatan pada pelaku Usaha Mikro; untuk mengetahui pengaruh
teknologi informasi terhadap pendapatan pada pelaku Usaha Mikro;
untuk mengetahui pengaruh etika bisnis Islam terhadap pendapatan pada
pelaku Usaha Mikro; untuk mengetahui pengaruh literasi keuangan,
teknologi informasi, dan etika bisnis Islam terhadap pendapatan pada
pelaku Usaha Mikro di Kecamatan Gedung Surian dan Kebun Tebu.
Dalam penelitian ini penulis menggunkan metode pendekatan
secara kuantitatif. Sumber data yang digunakan dalam penelitian ini
adalah sumber data primer dan sekunder. Dalam penelitian ini yang
dimaksud populasi adalah keseluruhan subjek penelitian, yaitu pelaku
usaha mikro yang ada di Kecamatan Gedung Surian dan Kebun Tebu.
Pelaku Usaha Mikro yang ada di Kecamatan Gedung Surian dan Kebun
Tebu secara keseluruhan berjumlah 1514 pelaku usaha mikro. Sampel
yang digunakan dalam penelitian ini diambil menggunakan teknik
purposive sampling. Jumlah sampel pada penelitian ini sebanyak 94
pelaku usaha mikro. Teknik pengumpulan data dalam penelitian ini
adalah kuesioner, observasi, dan dokumentasi. Metode analisis data
dalam penelitian ini menggunakan uji asumsi klasik, uji regresi linier
berganda, uji t, uji F dan uji koefisien determinasi.
Berdasarkan hasil penelitian yang telah dilakukan, dapat
disimpulkan bahwa: 1) Literasi Keuangan berpengaruh positif dan
signifikan terhadap pendapatan Usaha Mikro di Kecamatan Gedung
Surian dan Kebun Tebu; 2) Teknologi Informasi berpengaruh positif dan
signifikan terhadap pendapatan Usaha Mikro di Kecamatan Gedung
Surian dan Kebun Tebu; 3) Etika Bsinis Islam berpengaruh positif dan
signifikan terhadap pendapatan Usaha Mikro di Kecamatan Gedung
Surian dan Kebun Tebu; 4) Literasi keuangan, teknologi informasi, dan
etika bisnis Islam secara simultan berpengaruh signifikan terhadap
pendapatan Usaha Mikro di Kecamatan Gedung Surian dan Kebun Tebu ABSTRACT
Indonesia is a developing country still undertaking development
efforts. One of the development efforts currently underway in
Indonesia is economic development. Economic development leads to
job opportunities and sustainable economic growth. The objectives of
this study are to determine the effect of financial literacy on increasing
income among micro-entrepreneurs; to determine the effect of
information technology on increasing income among microentrepreneurs; to determine the effect of Islamic business ethics on
increasing income among micro-entrepreneurs; and to determine the
effect of financial literacy, information technology, and Islamic
business ethics on income among micro-entrepreneurs in Gedung
Surian and Tebu Districts.
In this study, the author used a quantitative approach. The data
sources used in this study were primary and secondary data sources. In
this study, the population refers to all research subjects, namely microentrepreneurs in Gedung Surian and Kebun Tebu Districts. There are
1,514 micro-entrepreneurs in Gedung Surian and KebunTebu
Districts. The sample used in this study was drawn using a purposive
sampling technique. The total sample size was 94 microentrepreneurs. The data collection techniques used in this study were
questionnaires, observation, and documentation. The data analysis
methods used were the classical assumption test, multiple linear
regression, t-test, F-test, and coefficient of determination test.
Based on the research results, it can be concluded that: 1)
Financial literacy has a positive and significant effect on microenterprise income in Gedung Surian and Kebun Tebu Districts; 2)
Information technology has a positive and significant effect on microenterprise income in Gedung Surian and Kebun Tebu Districts; 3)
Islamic business ethics has a positive and significant effect on microenterprise income in Gedung Surian and Kebun Tebu Districts; 4)
Financial literacy, information technology, and Islamic business ethics
simultaneously have a significant effect on micro-enterprise income in
Gedung Surian and Kebun Tebu Districts
VALIDATION OF SRAC CODE SYSTEM FOR NEUTRONIC PARAMETERS CALCULATION OF THE PWR MOX/UO2 CORE BENCHMARK
Get PDFVALIDATION OF SRAC CODE SYSTEM FOR NEUTRONIC PARAMETERS CALCULATION OF THE PWR MOX/UO2 CORE BENCHMARK. Determination of neutronic parameter value is an important part in determining reactor safety, so accurate calculation results can be obtained. This study is focused on the validation of SRAC code system in the calculation of neutronic parameters value of a PWR (Pressurized Water Reactor) reactor core. MOX/UO2 Core Benchmark was choosed because it is used by several researchers as a reference core for code validation in the determination of neutronic parameters of a reactor core. The neutronic parameters calculated include critical boron concentration, delayed neutron fraction, and Power Peaking Factor (PPF) and its distribution in axial and radial directions. When compared with reference data, the calculation results of the critical boron concentration value show that there is a difference of 22.5 ppm on SRAC code system. Meanwhile, differences in power per fuel element (assembly power error) value of power-weighted error (PWE) and error-weighted error (EWE) is 2.93% and 3.94%, respectively. Maximum difference between PPF value in axial direction with reference reaches a value of 4.57%. SRAC calculation results also show consistency with the calculation results of other program packages or code. Results of this study indicate that SRAC code system is still quite accurate for the calculation of neutronic parameters of PWR reactor core benchmark. Therefore, SRAC code system can be used to calculate neutronic parameters of PWR reactor core, especially when using MOX (mixed oxide) fuel.
Keywords: Neutronic parameter, critical boron concentration, power peaking factor, SRAC code system
Effect of cross-sections data on calculated static neutronic parameters of PWR MOX/UO2 core transient benchmark case using NODAL3 code
Get PDFThis paper describes the effect of cross-section data generated by several codes on calculated neutronic parameters. The Pressurized Water Reactor Mixed Oxide and Uranium Oxide (PWR MOX/UO2) Core Transient Benchmark case was chosen because it has been used widely to validate neutronic codes. The cross-section data in this study will be generated by SRAC, Serpent, and HELIOS codes. The NODAL3 code will be used to calculate neutronic parameters from each cross-section. The neutronic parameters calculated by NODAL3 are the effective multiplication factor (keff), control rod worth, critical boron concentration, and power distribution under Hot Zero Power (HZP) conditions. The Power-Weighted Error (PWE) and Error-Weighted Error (EWE), as a measure of the relative error in fuel assembly power, are less than 5 %, indicating that the calculation is consistent with DeCART as a reference. The difference in calculated radial power peaking factor for all three cross-sections to reference data reaches 6.284 % (G-3), 8.438 % (G-3), and 10.998 % (C-7), respectively, for SRAC, Serpent, and HELIOS. The axial power distribution calculated by NODAL3 at the top and bottom of the reactor core has a relative error that peaked at 16.60 %, 13.86 %, and 10.20 %, respectively, for cross-sections provided by SRAC, Serpent, and HELIOS. Further improvements are needed for NODAL3 by applying various discontinuity factors to improve its performance
Efek kerapatan bahan bakar U9-Mo/Al pengayaan rendah terhadap parameter kinetik reaktor riset jenis MTR
No full textAbstrak Reaktor riset umumnya memerlukan fluks netron yang tinggi agar iradiasi sampel dalam teras reaktor menjadi efektif. Fasilitas iradiasi tinggi dapat menghasilkan fluks netron tinggi bila reaktor didesain dengan teras kompak menggunakan bahan bakar kerapatan tinggi. Untuk mengetahui efek kerapatan bahan bakar dan reflektor pada parameter kinetik maka dilakukan perhitungan pada desain konsepsual teras reaktor riset inovatif (RRI). Teras RRI adalah teras kompak yang menggunakan bahan bakar U-9Mo/Al kerapatan tinggi sehingga penggunaan bahan bakar lebih ekonomis. Parameter kinetik yang akan dievaluasi dalam makalah ini adalah fraksi netron kasip efektif, umur generasi netron serempak dan konstanta peluruhan netron serempak. Akurasi perhitungan parameter tersebut dipengaruhi oleh dua hal yaitu tersedianya data tampang lintang netron untuk teras reaktor dan pemilihan metode dalam perhitungan parameter teras. Perhitungan sel bahan bakar dan batang kendali pada kondisi operasi reaktor menggunakan program WIMSD/5B. Parameter kinetik dihitung menggunakan program Batan-3DIFF. Hasil yang diperoleh menunjukkan bahwa harga umur netron serempak dan fraksi netron kasip berkurang dengan naiknya kerapatan bahan bakar sementara konstanta peluruhan netron serempak naik dengan naiknya kerapatan bahan bakar. Kerapatan bahan bakar 5,34 gU/cm3 dan reflektor D2O mempunyai keselamatan melekat yang paling aman karena mempunyai umur netron serempak dan fraksi netron kasip terbesar. Teras RRI dengan kerapatan 5,34 gU/cm3 dan reflektor D2O menghasilkan fraksi netron kasip sebesar 7,14917E-03 dan umur netron serempak 5,99216E-05 serta konstanta peluruhan netron serempak adalah 119,30 1/s. Kata kunci: kerapatan bahan bakar, parameter kinetik, Batan-3DIFF, reaktor RRI Abstract Research reactors generally require high flux neutron so that samples irradiation in the reactor core becomes effective. In order to be able to provide a high neutron flux in the irradiation facilities then the reactor is designed by a compact core using high density fuel. To see the effect of fuel density and reflector on the kinetic parameter then it has been calculated for the conceptual design of the reactor core RRI. RRI is compact core and uses high density U-9Mo/Al fuel so more economical. Kinetic parameters to be evaluated in this paper is effective delay neutron fraction, promt neutron generation time and promt neutron decay constant. Accuracy of the calculation of these parameters is influenced by two factors that are availability of the neutron cross-sections data and the selection of reactor core parameters calculation method. Calculation of fuel cells and the control rods in the reactor operating conditions were carried out by WIMSD/5B code. Kinetic parameters were calculated using the Batan-3DIFF code. The results showed that the effective delay neutron fraction, prompt neutron generation time decreases while promt neutron decay constant increase with increasing density of the fuel. Density of the fuel 5.34 gU/cm3 and D2O reflector have inherent safety of the safest because effective delay neutron fraction and promt neutron generation time are at the largest. RRI core using fuel density 5.34 gU/cm3 and D2O reflector showed results of effective delay neutron fraction is 7.14917 E-03, prompt neutron generation time is 5.99216 E-05 s and promt neutron decay constant is 119.30 1/s. Keywords : fuel density, kinetic parameters, Batan-3DIFF, RRI reacto
CALCULATION OF 2-DIMENSIONAL PWR MOX/UO2 CORE BENCHMARK OECD NEA 6048 WITH SRAC CODE
Get PDFThe mixed uranium-plutonium oxide fuel (MOX/UO2) is an interesting fuel for future power reactors. This is due to the large amount of plutonium that can be processed from spent fuel of nuclear plants or from plutonium weapons. MOX/UO2 fuel is very flexible to be applied in thermal reactors such as PWR and it is more economical than UO2 fuel. However, due to the different nature of neutron interactions of MOX in PWR, it will change the reactor core design parameters and also its safety characteristic. The purpose of this study is to determine the accuracy of SRAC2006 code system in generation of cross-sections and calculation of reactor core design parameters such as criticality, reactivity of control rods and radial power distribution. In this study, PWR MOX/UO2 Core Transient Benchmark is used to verify the code that models a MOX/UO2 fueled core. SRAC-CITATION result is different from DeCART by 0.339% from. SRAC-CITATION result of single rod worth in All Rods Out (ARO) conditions are quite good with a maximum difference of 6.34% compared to BARS code and 4.74% compared to PARCS code. In All Rods In (ARI) condition, SRAC-CITATION results compared to the PARCS code is quite good where the maximum difference is 9.72%, but compared to BARS code, it spikes up to 33.24% at maximum difference. In the other case, overall radial power density results are quite good compared to the reference. Its maximum deviation from DeCART code is 5.325% in ARO condition and 6.234% in ARI condition. Based on the results of these calculations, SRAC code system can be used to generate cross-section and to calculate some neutronic parameters. Hence, it can be used to evaluate the neutronic parameters of the MOX/UO2 PWR core design.Keywords: MOX/UO2 fuel, Criticality, Power peaking factor, SRAC200
VALIDASI PAKET PROGRAM NODAL3 UNTUK KASUS STATIS BENCHMARK TERAS REAKTOR PWR
Get PDFVALIDASI PAKET PROGRAM NODAL3 UNTUK KASUS STATIS TERAS BENCHMARK REAKTOR PWR. Persamaan difusi neutron dengan metode nodal telah menjadi metode standar dalam perhitungan parameter neutronik teras reaktor daya air ringan, seperti reaktor air bertekanan (PWR) atau air mendidih (BWR), karena waktu komputasi yang cepat dan hasilnya akurat. Paket program NODAL3 telah dikembangkan untuk menyelesaikan persamaan difusi neutron dengan metode nodal polinom (PNM) dalam geometri 3-dimensi (3-D). Validasi hasil perhitungan NODAL3 untuk kasus statis teras benchmark reaktor PWR (Pressurized Water Reactor), seperti IAEA-2D, BIBLIS, KOEBERG dan IAEA-3D, disajikan dalam penelitian ini. Teras benchmark yang dipilih mewakili kasus 2-D dan 3-D dan mempunyai karaktristik yang berbeda, sehingga dapat menentukan keakuratan NODAL3 dari aspek neutronik yang luas. Parameter neutronik statis yang dihitung adalah faktor perlipatan efektif, keff, faktor puncak daya (FPD) dan profil distribusi FPD ke arah aksial. Dibandingkan dengan acuan, hasil perhitungan NODAL3 menunjukkan bahwa untuk nilai keff terdapat perbedaan maksimum sebesar 0,006% (Δk). Sedangkan untuk FPD radial dan FPD aksial maksimum, selisih maksimum dengan acuan masing-masing sebesar -0,006 dan 0,051. Untuk kasus 3-D, hasil perhitungan NODAL3 konsisten dengan hasil perhitungan paket program nodal tervalidasi PARCS dan NESTLE. Riset ini menunjukkan bahwa akurasi paket program NODAL3 dalam menghitung parameter neutronik teras benchmark reaktor PWR, baik kasus 2-D dan 3-D, menunjukkan hasil yang sangat memuaskan. Oleh karena itu, paket program NODAL3 siap untuk diaplikasikan dalam analisis neutronik reaktor PWR yang riil.Kata kunci : metode nodal, reaktor PWR, teras benchmark, faktor perlipatan efektif, faktor puncak day
DESIGN OF NEUTRONIC PARAMETERS OF MTR REACTOR USING WIMSD-5B/BATAN-FUEL CODES
Get PDFBATAN has three aging research reactors, so it is necessary to design a new, more modern MTR type reactor using high-density, low enrichment uranium molybdenum fuel. The thermal neutron flux at the irradiation position is an important concern in the design of research reactors. This analysis is performed using standard computer codes WIMSD-5B and Batan-FUEL. The purpose of this study is to analyze the effect of the core configuration with safety control rods and neutronic parameters using the diffusion method calculation. The reactor core consists of 16 fuel elements and four control rods placed in the 5 x 5 position of the grid plate and is loaded the reflector elements outside the core. The cycle length is also a concern, not less than 20 days, and the reactor can be operated safely with a power of 50 MW. The calculation results show that for the highest fuel loading, which is 450 grams of U7Mo/Al fuel with D2O as a reflector, it will provide the lowest thermal neutron flux at the center of the core irradiation position, namely 1.0 x1015 n/cm2s. The core fuel cycle length will be up to 39 days, meeting the expected acceptance and safety criteria
ANALYSIS OF REACTIVITY COEFFICIENT CHANGE DUE TO BURN UP IN AP1000 REACTOR CORE USING NODAL3
Get PDFOne of the important things in reactor safety is the value of inherent safety parameter namely reactivity coefficient. These inherent safety parameters are fuel and moderator temperature coefficients of reactivity. The objective of the study is to obtain the change of those reactivity coefficients as a function of fuel burn up during the cycle operation of AP 1000 reactor core. Fuel and moderator temperature coefficients of reactivity and in addition moderator density coefficient of reactivity were calculated using SRAC 2006 and NODAL3 computer codes. Cross section generation of all core material was done by SRAC 2006 Code. The calculation of core reactivity as a function of temperature and burn up were carried out using NODAL3 Code. The results show that all reactivity coefficients of AP 1000 reactor core are always negative during the operation cycles and the values are in a good agreement to the design. It can be concluded that the AP 1000 core has a good inherent safety of its fuelKeywords: reactivity coefficient, burn up, AP1000, NODAL3. ANALISIS PERUBAHAN KOEFISIEN REAKTIVITAS AKIBAT FRAKSI BAKAR TERAS REAKTOR AP1000 MENGGUNAKAN NODAL3. Salah satu hal yang sangat penting dalam analisis kecelakaan pada reactor daya adalah koefisien reaktivitas untuk mengontrol daya reaktor. Penelitian ini bertujuan menentukan koefisien reaktivitas akibat perubahan fraksi bakar pada reaktor AP1000. Koefisien reaktivitas yang akan dihitung adalah koefisien reaktivitas bahan bakar dan moderator yang sering disebut inherent factor. Selain itu juga akan dihitung koefisien konsentrasi boron dan kerapatan moderator. Semua koefisien reaktivitas ini dihitung saat terjadi perubahan fraksi bakar untuk mempertimbangkan produk fisi dan konsumsi bahan bakar. Perhitungan neutronik teras reactor disimulasi dengan menggunakan program SRAC2006 dan NODAL3. Perhitungan tampang lintang seluruh perangkat bahan bakar dan batang kendali reaktor AP1000 dilakukan dengan program SRAC2006. Perhitungan parameter neutronik sebagai fungsi temperature dan fraksi bakar dilakukan menggunakan program NODAL3. Perhitungan koefisien reaktivitas ditentukan berdasarkan perbedaan nilai reaktivitas. Hasil perhitungan menunjukkan bahwa koefisien reaktivitas teras reaktor AP 1000 selalu berharga negative untuk sepanjang siklus operasinya dan mendekati harga desain. Kesimpulan yang dapat ditarik adalah bahwa teras AP 10000 mempunyai keselamatan melekat yang baik.Kata kunci: koefisien reaktivitas, fraksi bakar, AP 1000, NODAL3.</jats:p
VALIDATION OF FULL CORE GEOMETRY MODEL OF THE NODAL3 CODE IN THE PWR TRANSIENT BENCHMARK PROBLEMS
Get PDFABSTRACT VALIDATION OF FULL CORE GEOMETRY MODEL OF THE NODAL3 CODE IN THE PWR TRANSIENT BENCHMARK PROBLEMS. The coupled neutronic and thermal-hydraulic (T/H) code, NODAL3 code, has been validated in some PWR static benchmark and the NEACRP PWR transient benchmark cases. However, the NODAL3 code have not yet validated in the transient benchmark cases of a control rod assembly (CR) ejection at peripheral core using a full core geometry model, the C1 and C2 cases. By this research work, the accuracy of the NODAL3 code for one CR ejection or the unsymmetrical group of CRs ejection case can be validated. The calculations by the NODAL3 code have been carried out by the adiabatic method (AM) and the improved quasistatic method (IQS). All calculated transient parameters by the NODAL3 code were compared with the reference results by the PANTHER code. The maximum relative difference of 16% occurs in the calculated time of power maximum parameter by using the IQS method, while the relative difference of the AM method is 4% for C2 case. All calculation results by the NODAL3 code shows there is no systematic difference, it means the neutronic and T/H modules are adopted in the code are considered correct. Therefore, all calculation results by using the NODAL3 code are very good agreement with the reference results. Keywords: nodal method, coupled neutronic and thermal-hydraulic code, PWR, transient case, control rod ejection. ABSTRAK VALIDASI MODEL GEOMETRI TERAS PENUH PAKET PROGRAM NODAL3 DALAM PROBLEM BENCHMARK GAYUT WAKTU PWR. Paket program kopel neutronik dan termohidraulika (T/H), NODAL3, telah divalidasi dengan beberapa kasus benchmark statis PWR dan kasus benchmark gayut waktu PWR NEACRP. Akan tetapi, paket program NODAL3 belum divalidasi dalam kasus benchmark gayut waktu akibat penarikan sebuah perangkat batang kendali (CR) di tepi teras menggunakan model geometri teras penuh, yaitu kasus C1 dan C2. Dengan penelitian ini, akurasi paket program NODAL3 untuk kasus penarikan sebuah CR atau sekelompok CR yang tidak-simetris dapat divalidasi. Perhitungan paket program NODAL3 dilakukan dengan metode adiabatic (AM) dan improved quasistatic (IQS). Seluruh parameter gayut waktu hasil perhitungan paket program NODAL3 dibandingkan dengan hasil acuan dengan paket program PANTHER. Perbedaan relatif maksimum sebesar 16% terjadi dalam perhitungan parameter waktu daya maksimum dengan metode IQS pada kasus C2, sedangkan perbedaan relatif dengan metode AM adalah 4%. Seluruh hasil perhitungan dengan paket program NODAL3 menunjukkan tidak adanya perbedaan yang sistematis, berarti modul neutronik dan T/H yang diadopsi di NODAL3 sudah benar. Oleh karena itu, seluruh perhitungan dengan paket program NODAL3 sangat sesuai dengan hasil acuan. Kata kunci: metode nodal, paket program kopel neutonik dan termo-hidrolika, kasus gayut-waktu, tertariknya batang kendali.</jats:p
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