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Iqbal Firdaus
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Journal : Jurnal Teori dan Aplikasi Fisika

 1 
Solusi Persamaan Difusi Neutron pada Pressurized Water Reactor (PWR) Berbentuk Silinder dengan Bahan Bakar Uranium Daur Ulang Riftaul Kurniawati; Yanti Yulianti; Iqbal Firdaus
Jurnal Teori dan Aplikasi Fisika Vol 11, No 2 (2023): Jurnal Teori dan Aplikasi Fisika
Publisher : Universitas Lampung

Show Abstract | Download Original | Original Source | Check in Google Scholar | DOI: 10.23960/jtaf.v11i2.6645

Abstract

The Research on solution of the neutron diffusion equation in a cylindrical Pressurized Water Reactor (PWR) with recycled uranium fuel. The research aims to obtain the distribution of neutron flux in a cylindrical Pressurized Water Reactor (PWR) using recycled uranium fuel. The method was carried out by means of simulations using the C++ programming language including determining the specifications of the reactor core, determining cell geometry and volume fraction, determining atomic density, calculating macroscopic cross-sections with the PIJ module, and calculating the neutron diffusion equation. After obtaining the solution of the neutron diffusion equation, calculations were carried out on ¼ part of the reactor core with a cylindrical cell geometry defined by IGT=3 on SRAC. The results obtained in this study are that the diffusion equation without a source of distribution of the highest neutron flux is in group 1 of 1.1681 × 10-10, the diffusion equation with a fission source of the highest distribution of neutron flux is in group 3 of 4.6009 × 10 -8, the diffusion equation with fission sources and the scattering distribution of the highest neutron flux is in group 3 with the division time of 1.1681 × 10-10, the diffusion equation with fission sources changes the power of 3,000 MW the highest distribution of neutron flux is in the group 3. The highest group has more neutron flux and changes in power do not affect the value of the neutron flux.
Solusi Persamaan Difusi Neutron Pada PWR (Pressurized Water Reactor) Berbentuk Heksagonal dengan Bahan Bakar Uranium Daur Ulang Risdha Ayu Shinta Dewi; Yanti Yulianti; Iqbal Firdaus
Jurnal Teori dan Aplikasi Fisika Vol 11, No 2 (2023): Jurnal Teori dan Aplikasi Fisika
Publisher : Universitas Lampung

Show Abstract | Download Original | Original Source | Check in Google Scholar | DOI: 10.23960/jtaf.v11i2.6646

Abstract

The Research on solution of the neutron diffusion equation with a PWR reactor using recycled uranium fuel at 1⁄6 section of the reactor core with a hexagonal IGT-6 geometry. The purpose of this research is to determine the distribution of the neutron flux in the PWR of recycled uranium fuel. The solution is done by computational simulation using the Dev-C++ programming. The parameters used in this study determine the specifications of the reactor core, determine the volume fraction, determine the atomic density, calculate the macroscopic cross-section with the PIJ module, calculate the neutron diffusion equation, calculate ϕ (x,y) using the Gauss Seidel method. The results obtained in this study are the neutron diffusion equation without a source obtaining the highest relative neutron flux value in group 1 of 4,5729×〖10〗^(-2), with a fission source obtaining the highest relative neutron flux value in group 3 of 7,3327×〖10〗^(-4), with fission and scattering sources obtaining the highest relative neutron flux value found in group 2 of 1,5157×〖10〗^(-3), and 3,200 MW of power is added to the source fission, the value of the neutron flux does not change. This is because the addition of power does not affect the value of the neutron flux.
Co-Authors Abdul Kadir Agus Aan Adriansyah Ahmad Raihan Akas Yekti Pulih Asih Budhi Setianto Diah Sudiarti Dini Rusqiati Effendy Effendy Eliasta Ketaren Evy Afifah Syagran Henny Septiana Amalia Mahardika I. Takaendengan Masithah Akbar Melda Sari Muhammad Maladi Muhammad Zahid Abdillah Nikita Laurencia Nikmatus Sa’adah Nirza Marzuki Husein Norbaiti Normalina Punda Susanto R.R Siti Munawaroh Riftaul Kurniawati Rio Adi Saputra Risdha Ayu Shinta Dewi Riswan Ludfi Rizky Nastiti Saifhul Anuar Syahdan silvia ratna Siska Ayu Widiana Tenda, Edwin Tri Ramaraya Koroy Umi Hanik Yanti Yulianti Yanuar Bachtiar