Analisis Densitas Nuklida Lead-Bismuth Cooled Fast Reactor (LFR) Bedasarkan Variasi Daya Keluaran

Authors

  • Cici Rahmadya Guskha Jurusan Fisika FMIPA Universitas Andalas
  • Mohammad Ali Shafii Jurusan Fisika FMIPA Universitas Andalas
  • Feriska Handayani Irka Jurusan Fisika FMIPA Universitas Andalas
  • Zaki Su’ud Jurusan Fisika Institut Teknologi Bandung

DOI:

https://doi.org/10.25077/jfu.5.1.7-13.2016

Abstract

Analisis densitas nuklida Lead-bismuth Cooled Fast Reactor (LFR) berdasarkan variasi daya keluaran telah dilakukan. Reaktor ini menggunakan UN-PuN sebagai bahan bakar dan timbal-bismuth sebagai pendingin. Parameter yang diamati adalah Inte.C.R (Integral Convertion Ratio) dan densitas nuklida (235U, 238U, 239Pu).  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 axial. 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 simulasi menunjukkan bahwa daya 300 MWTh mempunyai nilai Inte.C.R dan densitas nuklida yang paling optimal (memiliki nilai yang paling besar dibandingkan dengan daya keluaran yang lain sehingga bisa digunakan dalam pengoperasian reaktor dalam jangka panjang).

Kata kunci: burn up, densitas nuklida, LFR, shuffling, UN-PuN.

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Published

2016-01-01

How to Cite

Guskha, C. R., Shafii, M. A., Irka, F. H., & Su’ud, Z. (2016). Analisis Densitas Nuklida Lead-Bismuth Cooled Fast Reactor (LFR) Bedasarkan Variasi Daya Keluaran. Jurnal Fisika Unand, 5(1), 7–13. https://doi.org/10.25077/jfu.5.1.7-13.2016

Issue

Vol. 5 No. 1 (2016)

Section

Articles

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Copyright (c) 2016 Cici Rahmadya Guskha, Mohammad Ali Shafii, Feriska Handayani Irka, Zaki Su’ud

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