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The Analytical Solutions of the Schrodinger Equation for a Single Electron in the Nikiforov-Uvarov Framework Yulianto, Yacobus; Su'ud, Zaki
Jurnal Fisika Vol 10, No 2 (2020)
Publisher : Universitas Negeri Semarang

Show Abstract | Download Original | Original Source | Check in Google Scholar | DOI: 10.15294/jf.v10i2.25190

Abstract

In this study, it is intended to show an alternative method to derive the wave function of a single electron as solutions of the Schrodinger equation. The Nikiforov-Uvarov method was chosen to be utilized since this method can solve the Schrodinger equation with several well-known potentials in the non-relativistic mechanics of quantum. The obtained results of this study have succeed to explain the wave function and the energy eigenvalue for a single electron as lectured in quantum physics textbooks. These results prove that the Nikiforov-Uvarov method provides an alternative procedure to solve the Schrodinger equation.
The Effect of Burnable Poison Np-237 on the Conceptual Design of the GFR-2400 MWt Using MCANDLE Burnup Strategy Monado, Fiber; Berliani, Berliani; Supardi, Supardi; Royani, Idha; Ariani, Menik; Kaban, Hadir; Su'ud, Zaki
POSITRON Vol 14, No 1 (2024): Vol. 14 No. 1 Edition
Publisher : Fakultas Matematika dan Ilmu Pengetahuan Alam, Univetsitas Tanjungpura

Show Abstract | Download Original | Original Source | Check in Google Scholar | DOI: 10.26418/positron.v14i1.65433

Abstract

This study was used to design the Gas-cooled Fast Reactor (GFR) with 2400 MWt power as well as to implement a modified CANDLE (MCANDLE) burning strategy. Metallic uranium with Neptunium-237 at a concentration of 1% to 10% was used as burnable poison in the fuel while helium was applied as a coolant. Neptunium has been produced in conventional reactors by the decay product of plutonium obtained from U-238. This isotope has a relatively high absorption cross-section. As a nuclear waste, it is very useful to utilize as a burnable poison to reduce waste in the future and extend reactor operation lifetime with negligible reactivity. Moreover, the reactor was designed to operate for 100 years of burnup. Nuclear Fuel cell level calculations were conducted using the PIJ module and the reactor core was analyzed using the CITATION module contained in the SRAC. The core height was found to be 420 cm while the diameter was 300 cm and it was designed to have a refueling period of ten years. The survey parameters evaluated include burnup level, factor multiplication, conversion ratio, atomic density, and power distribution. The calculation conducted at the fuel cell level showed that the maximum value in the 76th year for the infinite multiplication factor was 1.30097. It was also discovered that the reactor core for the effective multiplication factor parameter with a fuel fraction of 55% was 1.094 without the addition of burnable poison.
Analisis Kekritisan dan Rasio Konversi Reaktor Cepat Berpendingin Gas dengan Variasi Fraksi Bahan Bakar UN-PuN Menggunakan Skema Burn-up Modified CANDLE Arah Radial Irka, Feriska Handayani; Su'ud, Zaki; Irwanto, Dwi; Khotimah, Siti Nurul; Sekimoto, Hiroshi
Newton-Maxwell Journal of Physics Vol. 4 No. 1: April 2023
Publisher : UNIB Press

Show Abstract | Download Original | Original Source | Check in Google Scholar | DOI: 10.33369/nmj.v4i1.27127

Abstract

Analysis of the criticality and conversion ratio of a gas-cooled fast reactor (GFR) with various UN-PuN fuel fractions using modified CANDLE scheme burn-up in radial direction has been conducted. The fuel fraction varies from 40% - 60% with 5% intervals, the cladding fraction is 10% and the coolant fraction varies from 30% -50%. Data calculations were performed using SRAC 2006 programming with JENDL 4.0 library data. The reactor is divided into 10 regions with equal volume in the radial direction. Each region is filled with natural uranium fuel without enrichment with different burn-up levels. Regions are arranged in such a way that the reactor can reach critical conditions throughout the burn-up period. The results showed that variations in the 40% fuel fraction had not been able to reach critical conditions at the beginning of life, while 45%-60% fuel fraction variations had reached reactor criticality. The conversion ratio for all fuel fractions is greater than 1, which indicates that a breeding process appears in the GFR reactor core.  The conversion ratio for all variations in fuel fractions has almost the same pattern for all regions. The first region has the largest conversion ratio value because it has natural uranium as fuel input which has the highest density compared to other regions.  
Analisis Kekritisan Sodium-Cooled Fast Reactor (SFR) Berdasarkan Variasi Bahan Bakar Septi, Revina; Shafii, Mohammad Ali; Irka, Feriska Handayani; Su'ud, Zaki
Jurnal Fisika Unand Vol 7 No 1 (2018)
Publisher : Universitas Andalas

Show Abstract | Download Original | Original Source | Check in Google Scholar | DOI: 10.25077/jfu.7.1.69-72.2018

Abstract

Analisis kekritisan Sodium-Cooled Fast Reactor (SFR) berdasarkan variasi bahan bakar telah dilakukan. Variasi bahan bakar yang digunakan adalah MOX, UN-PuN, dan U-Zr. Reaktor ini menggunakan natrium sebagai pendingin dan parameter yang diamati adalah faktor multiplikasi (keff )pada teras reaktor. Penelitian ini dilakukan secara simulasi komputasi meggunakan kode SRAC (Standard Thermal Reactor Analysis Code System) dengan JENDL-32 sebagai library. Teras reaktor dibagi menjadi 10 region arah radial.  Pada awal operasi reaktor, masing-masing region diisi dengan bahan bakar uranium alam.  Setelah 10 tahun pembakaran, hasil burn up pada region 1 di shuffling ke region 2, hasil region 2 di shuffling ke region 3 dan seterusnya sampai hasil burn up di region 9 di shuffling ke region 10, hasil burn up region 10 dikeluarkan dari teras reaktor dan pada region 1 akan diisi dengan bahan bakar yang baru. Hasil penelitian menunjukkan bahwa bahan bakar MOX dan U-Zr memilki nilai keff  yang paling optimal digunakan pada reaktor SFR.Kata kunci: faktor multiplikasi keff , periode burn up, program SRAC, strategi shuffling
Analisis Kekritisan Lead-Cooled Fast Reactor (LFR) Berdasarkan Variasi Bahan Bakar (U-Zr dan UN-PuN) Munita, Lidia; Shafii, Mohammad Ali; Irka, Feriska Handayani; Su'ud, Zaki
Jurnal Fisika Unand Vol 7 No 1 (2018)
Publisher : Universitas Andalas

Show Abstract | Download Original | Original Source | Check in Google Scholar | DOI: 10.25077/jfu.7.1.80-83.2018

Abstract

Telah dilakukan analisis kekritisan Lead-Cooled Fast Reactor (LFR) menggunakan program SRAC. Reaktor ini menggunakan Pb-Bi sebagai pendingin. Analisis kekritisan LFR dilakukan dengan menvariasikan jenis bahan bakar yaitu uranium-plutonium nitrida (UN-PuN) dan uranium-zirkonium (U-Zr). Parameter neutronik yang dianalisis adalah faktor multiplikasi neutron (keff). Pada penelitian ini digunakan metode shuffling. Metode shuffling digunakan agar reaktor dapat beroperasi tanpa pengayaan dan menggunakan uranium alam sebagai bahan bakar. Teras reaktor dibagi menjadi 11 region arah radial. Sepuluh region pertama digunakan untuk menempatkan bahan bakar dan region ke-11 sebagai reflektor. Pada awal operasi reaktor, masing-masing region diisi dengan bahan bakar uranium alam yang telah di burn up terlebih dahulu. Setelah 10 tahun pembakaran, hasil burn up pada region 1 di shuffling ke region 2, hasil burn up region ke-2 di shuffling ke region 3, begitu seterusnya sampai hasil burn up region ke-9 di shuffling ke region 10 dan hasil burn up region ke-10 dikeluarkan dari teras reaktor sehingga region 1 dapat diisi dengan bahan bakar baru dan begitu seterusnya sampai 100 tahun operasi reaktor. Hasil yang diperoleh menunjukkan bahwa bahan bakar UN-PuN lebih optimal dibandingkan bahan bakar U-Zr. Hal ini ditunjukkan oleh nilai keff yang diperoleh pada bahan bakar UN-PuN lebih tinggi dibandingkan U-Zr untuk fraksi bahan bakar yang sama.Kata kunci : keff, LFR, SRAC, UN-PuN, U-Zr, strategi shuffing.