STUDI PEMODELAN DAN PERHITUNGAN TRANSPORT MONTE CARLO DALAM TERAS HTR PEBBLE BED
DOI:
https://doi.org/10.26740/jpfa.v2n2.p1-9Keywords:
kernel, TRISO, bahan bakar pebble, HTR pebble bed, MCNP5Abstract
Konsep sistem energi VHTR baik yang berbahan bakar pebble (VHTR pebble bed) maupun blok prismatik (VHTR prismatik) menarik perhatian fisikawan reaktor nuklir. Salah satu kelebihan teknologi bahan bakar bola adalah menawarkan terobosan teknologi pengisian bahan bakar tanpa harus menghentikan produksi listrik. Selain itu, partikel bahan bakar pebble dengan kernel uranium oksida (UO2) atau uranium oksikarbida (UCO) yang dibalut TRISO dan pelapisan silikon karbida (SiC) dianggap sebagai opsi utama dengan pertimbangan performa tinggi pada burn-up bahan bakar dan temperatur tinggi. Makalah ini mendiskusikan pemodelan dan perhitungan transport Monte Carlo dalam teras HTR pebble bed. HTR pebble bed adalah reaktor berpendingin gas temperatur tinggi dan bermoderator grafit dengan kemampuan kogenerasi. Perhitungan dikerjakan denganprogram MCNP5 pada temperatur 1200 K. Pustaka data nuklir energi kontinu ENDF/B-V dan ENDF/B-VI dimanfaatkan untuk melengkapi analisis. Hasil perhitungan secara keseluruhan menunjukkan konsistensi dengan nilai keff yang hampir sama untuk pustaka data nuklir yang digunakan. Pustaka ENDF/B-VI (66c) selalu memproduksi keff lebih besar dibandingkan ENDF/B-V (50c) maupun ENDF/B-VI (60c) dengan bias kurang dari 0,25%. Kisi BCC memprediksi keff hampir selalu lebih kecil daripada kisi lainnya, khususnya FCC. Nilai keff kisi BCC lebih dekat dengan kisi FCC dengan bias kurang dari 0,19% sedangkan dengan kisi SH bias perhitungannya kurang dari 0,22%. Fraksi packing yang sedikit berbeda (BCC= 61%, SH= 60,459%) tidak membuat bias perhitungan menjadi berbeda jauh. Estimasi keff ketiga model kisi menyimpulkan bahwa model BCC lebih bisa diadopsi dalam perhitungan HTR pebble bed dibandingkan model FCC dan SH. Verifikasi hasil estimasi ini perlu dilakukan dengan simulasi Monte Carlo atau bahkan program deterministik lainnya guna optimisasi perhitungan teras reaktor temperatur tinggi.References
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Radiation Shielding Center, œDLC-105/MCNPDAT: Standard Neutron Cross Section Data Library Derived from ENDF/B-V for MCNP Version 4, 1994.
J.S. Hendricks, S.C. Frankle, and J.D. Court, œ ENDF/B-VI Data for MCNP, Los Alamos National Laboratory Report, LA-12891, 1994.
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Published
2012-12-14
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Zuhair, Z. (2012) “STUDI PEMODELAN DAN PERHITUNGAN TRANSPORT MONTE CARLO DALAM TERAS HTR PEBBLE BED”, Jurnal Penelitian Fisika dan Aplikasinya (JPFA), 2(2), pp. 1–9. doi: 10.26740/jpfa.v2n2.p1-9.
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