PERHITUNGAN PENAMPANG LINTANG MIKROSKOPIK DALAM SEL BAHAN BAKAR NUKLIR
Abstract
Abstrak
Perhitungan penampang lintang mikroskopik sel bahan bakar nuklir sangat penting dilakukan untuk menentukan distribusi fluks neutron dalam teras reaktor nuklir, karena distribusi fluks yang merata akan menentukan daya reaktor. Library data nuklir yang digunakan dalam penelitian ini adalah JFS-3-J33-70g yang dipakai oleh kode komputer SLAROM dari JAEA (Japan Atomic Energi Agency). Secara garis besar proses perhitungan adalah sebagai berikut; membaca data dari library SLAROM JFS-33 berdasarkan pada masukan spesifikasi sel bahan bakar nuklir. Kemudian menginterpolasi dari tabulasi nilai-nilai sebagai fungsi penampang lintang latar dan suhu. Selanjutnya menghitung penampang lintang latar awal untuk koreksi heterogenitas menggunakan pendekatan Wigner dengan memasukkan faktor Dancoff dan Bell. Interpolasi dengan metode cubic spline baik terhadap variabel temperatur maupun penampang lintang latar dilakukan lagi untuk mendapatkan penampang lintang serapatan dan hamburan total. Dari hasil perhitungan, nilai penampang lintang fisi, capture, elastik dan tak elastik nuklida U-235 memberikan hasil yang sesuai dengan referensi.
Abstract
Calculation of microscopic cross section of nuclear fuel cell need to be done to determine the distribution of neutron flux in the nuclear reactor core, because the distribution of flux evenly will determine the power reactor. Nuclear data library that is used in this research is the JFS-3-70-J33 used by SLAROM computer code from JAEA (Japan Atomic Energy Agency). Generally the process of calculation are as follows; read data from library of SLAROM JFS-3-70-J33 based on input specifications of nuclear fuel cells. Futhermore, interpolatation of the tabulated values as a function of background cross section and temperature is done. Initial background cross section for heterogeneity correction is calculated using Wigner approach by inserting Dancoff and Bell factors. Interpolation by cubic splines method for the variable of temperature and background cross section is evaluated again to get an absorbtion and total scattering cross section. The results show that the microscopic fission, capture, elastic and inelastic cross section of U-235 isotope are in accordance with the reference.
Keywords: microscopic cross section, nuclear fuel cell, background cross section.
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