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All Journal SIGMA EPSILON - Majalah Ilmiah Teknologi Keselamatan Nuklir Urania Jurnal Ilmiah Daur Bahan Bakar Nuklir
Santo Paulus Rajagukguk
UNIMED
Computer Science & IT Energy Materials Science & Nanotechnology

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PERHITUNGAN SEL BAHAN BAKAR REAKTOR PWR DENGAN PROGRAM WIMSD-5B Santo Paulus Rajagukguk; Syaiful Bakhri; Tukiran Surbakti
SIGMA EPSILON - Buletin Ilmiah Teknologi Keselamatan Reaktor Nuklir Vol 24, No 2 (2020): November 2020
Publisher : Badan Tenaga Nuklir Nasional

Show Abstract | Download Original | Original Source | Check in Google Scholar | DOI: 10.17146/sigma.2020.24.2.5971

Abstract

Perhitungan sel bahan bakar teras reaktor PWR telah dilakukan dengan menggunakan  program komputer WIMSD-5B. Perhitungan dilakukan untuk mengetahui karakteristik neutronik bahan bakar teras reaktor PWR dengan variasi daya. Karakteristik neutronik diketahui dengan memperoleh konstanta makroskopik seperti k-inf, koefisien difusi, tampang lintang serapan dan fisi. Generasi sel bahan bakar dilakukan dengan 69 grup energi neutron pada program transport satu dimensi (WIMSD-5B) menggunakan ENDF-BVII.1 data file. Sel satuan diperhitungkan pada perangkat elemen bakar dengan model cluster dengan susunan square pitch, kemudian dihitung dimensi satuan selnya. Satu satuan sel terdiri dari satu satuan bahan bakar dan moderator. Dari satu satuan sel ekivalen tersebut diperoleh data dimensi sel sebagai data masukan program WIMSD-5B yang dikenal dengan annulus. Bahan bakar yang digunakan adalah UO2 dan bentuk geometrinya pin cell bahan bakar. Hasil perhitungan faktor multiplikasi tak terhingga sel teras PWR yang dihitung dengan menggunakan paket program WIMSD-5B adalah 1,302338 dan fraksi bakar 37,12 GWD/TU. Dari hasil perhitungan dapat dinyatakan bahwa nilai faktor multiplikasi tak terhingga, konstanta difusi, tampang lintang serapan dan nu-fisi sangat dipengaruhi oleh bentuk model yang digunakan.Kata kunci: bahan bakar, teras PWR, WIMSD-5B,  energi neutron, konstanta makroskopik 
NEUTRONIC CALCULATION FOR PWR MOX FUEL PIN CELLS WITH WIMSD-5B CODE Santo Paulus Rajagukguk; Syaiful Bakhri; Tukiran Surbakti
Urania : Jurnal Ilmiah Daur Bahan Bakar Nuklir Vol 28, No 1 (2022): Februari, 2022
Publisher : website

Show Abstract | Download Original | Original Source | Check in Google Scholar | DOI: 10.17146/urania.2022.28.1.6610

Abstract

NEUTRONIC CALCULATION FOR PWR MOX FUEL PIN CELLS WITH WIMSD-5B CODE. The WIMSD-5B thermal reactor lattice cell code is used in many laboratories for research reactor calculations and power reactors. The program uses the Wigner-Seitz approximation for cell pin calculations. The approximation has been widely applied to the pin of UO2 cells and has shown good results in previous studies but can produce incorrect results when used for pin cells in MOX fuels. This paper investigates the use of the WIMS-5B code to calculate the neutron multiplication factor and depletion for MOX fuel pin cells. Calculations were performed using the WIMSD-5B code updated with the ENDF-BVIII.0 library. The outer scattering boundary condition was used to overcome the effect of the Wigner-Seitz approach on the lack of MOX fuel. Results of this study indicates that most of the results obtained using ENDF-BVIII.0 are better than ENDF-BVII.1, and this is in line with expectations. The difference in the maximum k-inf value obtained from this library occurs in the fuel that has the greatest enrichment. On the other hand, the addition of the outer scattering limit improves the results obtained using ENDF-BVIII.0, causing a slight improvement for other libraries. This shows that by using appropriate libraries and the addition of the scattering outer limit, the Wigner Seitz approximation for the MOX pin cell pins in WIMS-D5 can yield quite accurate results.Keywords: Wigner-Seitz approximation, WIMS-D5 code, MOX fuel, Doppler reactivity.
Co-Authors Syaiful Bakhri Syaiful Bakhri Tukiran Surbakti Tukiran Surbakti