%A NIM. 10620012 NUR HIDAYAH 
%O Pembimbing :  Dr. Suharyana, M.Sc


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

%X 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%.

%K Key Words: Fraction of fuel, LAK, MCNPX, nuclides, fission, fission products,
RSG-GAS reactor.

%D 2014
%I UNIVERSITAS ISLAM NEGERI SUNAN KALIJAGA
%L digilib14730