PERHITUNGAN BAHAN BAKAR YANG TERSISA PADA REAKTOR SERBA GUNA G.A. SIWABESSY (RSG-GAS) MENGGUNAKAN MCNPX

NUR HIDAYAH , NIM. 10620012 (2014) PERHITUNGAN BAHAN BAKAR YANG TERSISA PADA REAKTOR SERBA GUNA G.A. SIWABESSY (RSG-GAS) MENGGUNAKAN MCNPX. Skripsi thesis, UNIVERSITAS ISLAM NEGERI SUNAN KALIJAGA.

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Abstract

Calculations have been carried out on the remaining fuel Reactor Serba Guna G.A. Siwabessy (RSG-GAS) using the program package MCNPX. The method of calculating the residual fuel was performed using the program package MCNP applying the Monte Carlo method is statistical in finding the solution. Components or materials in the reactor is modeled in the form of geometry, dimensions and composition as close as possible to the original object. Calculation of residual fuel RSG-GAS reactor, the data size of the material needed materials referenced from Safety Analysis Reports (SARs). This data is needed to make the MCNPX input that is used to calculate the rest of the reactor fuel after the operation, by providing input in the form of characters long operation time, power, fractions, material and material specification numbers obtained MCNPX output results in the form of fuel mass. Output is obtained, it is known that there are many new nuclides formed from the cleavage of fission product having a different mass. This occurs because the mass of fission products are not always exactly the same, but it varies. Furthermore, the mass of the fuel burn up calculation. The result is the amount of fuel remaining fraction of the RSG-GAS reactor after operating for successive 3, 4, 5 and 6 days of 97.511%, 97.516%, 97.522% and 97.528%.

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