Analisis Kekritisan Sodium-Cooled Fast Reactor (SFR) Berdasarkan Variasi Daya Keluaran

Authors

  • Elsa Yolanda Putri Jurusan Fisika FMIPA Universitas Andalas
  • Mohammad Ali Shafii Jurusan Fisika FMIPA Universitas Andalas
  • Feriska Handayani Irka Jurusan Fisika FMIPA Universitas Andalas
  • Zaki Su'ud LaboratoriumNuklir dan Biofisika Institut Teknologi Bandung

DOI:

https://doi.org/10.25077/jfu.7.1.45-49.2018

Abstract

Analisis kekritisan Sodium-Cooled Fast Reactor (SFR) berdasarkan  variasi daya keluaran telah dilakukan. Reaktor ini menggunakan uranium alam sebagai bahan bakar dan natrium sebagai pendingin. Parameter yang diamati adalah faktor multiplikasi (keff  dan kinf ). Penelitian ini dilakukan secara simulasi komputasi menggunakan kode SRAC dengan JENDL-32 sebagai library.  Model teras adalah cylinder dua dimensi R-Z dengan  lima  variasi daya keluaran yaitu 300, 350, 400, 450, dan 500 MWTh. Teras reaktor dibagi menjadi 11 region radial dan 2 region aksial. Sepuluh region pertama merupakan region untuk menempatkan bahan bakar sedangkan region ke sebelas adalah reflektor. 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 burn up region 2 di shuffling ke region 3, dan seterusnya sampai hasil burn up region 9 di shuffling ke region 10 dan hasil burn up region 10 dikeluarkan dari teras reaktor sehingga region 1 dapat diisi dengan  bahan bakar baru (fresh fuel).  Proses ini dilakukan sampai 100 tahun operasi reaktor. Hasil penelitian menunjukkan bahwa daya keluaran 300 MWTh mempunyai nilai kekritisan yang mendekati nilai 1 (reaktor dalam keadaan kritis menandakan jumlah populasi neutron pada satu generasi sama dengan generasi sebelumnya).

Kata kunci: burn up, kekritisan, SFR, shuffling, uranium alam.

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Published

2017-01-03

Issue

Vol. 7 No. 1 (2018)

Section

Articles

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