Analisis Koefisien Difusi Neutron terhadap Jarak Ekstrapolasi dalam Persamaan Difusi Multigrup Satu Dimensi

Authors

  • Winka Wino Yunanda Laboratorium Fisika Nuklir, Jurusan Fisika, Fakultas Matematika dan Ilmu Pengetahuan Alam Universitas Andalas
  • Mohammad Ali Shafii Laboratorium Fisika Nuklir, Jurusan Fisika, Fakultas Matematika dan Ilmu Pengetahuan Alam Universitas Andalas

DOI:

https://doi.org/10.25077/jfu.8.4.362-367.2019

Abstract

Telah dilakukan analisis koefisien difusi neutron terhadap jarak ekstrapolasi dalam persamaan difusi multigrup satu dimensi. Penelitian ini bertujuan untuk menentukan distribusi fluks neutron yang selanjutnya digunakan sebagai nilai masukan untuk menghitung koefisien difusi neutron sebagai fungsi 70 grup energi. Jenis reaktor yang digunakan dalam penelitian ini adalah reaktor cepat dengan teras berbentuk slab dan bahan bakar yang digunakan adalah U-PuN. Pada penelitian ini dilakukan perhitungan distribusi fluks neutron dan koefisien difusi neutron untuk 20 grup energi yaitu hanya pada grup energi tinggi saja. Hasil penelitian menunjukkan bahwa nilai koefisien difusi pada 20 grup terhadap jarak ekstrapolasi pada grup energi cepat untuk bahan bakar U-235 dan Pu-239 diperoleh nilai yang hampir sama yaitu antara 1x10-4cm sampai 5x10-4 cm hal ini terjadi karena U-235 dan Pu-239 merupakan bahan fisil, sedangkan nilai koefisien difusi neutron pada U-238 jauh lebih kecil yaitu antara 5x10-5cm sampai 25x10-5 cm, perbedaan nilai ini terjadi karena U-238 merupakan bahan fertil.

Kata kunci: distribusi fluks neutron, grup energi, jarak ekstrapolasi, koefisien difusi neutron

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Published

2019-11-26

How to Cite

Yunanda, W. W., & Shafii, M. A. (2019). Analisis Koefisien Difusi Neutron terhadap Jarak Ekstrapolasi dalam Persamaan Difusi Multigrup Satu Dimensi. Jurnal Fisika Unand, 8(4), 362–367. https://doi.org/10.25077/jfu.8.4.362-367.2019

Issue

Vol. 8 No. 4 (2019)

Section

Articles

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Copyright (c) 2019 Winka Wino Yunanda, Mohammad Ali Shafii

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