Solusi Persamaan Difusi Neutron pada Pressurized Water Reactor (PWR) Berbentuk Silinder dengan Bahan Bakar Uranium Daur Ulang

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.