Institusion
Universitas Islam Negeri Sunan Kalijaga
Author
MASLIHATUN NI’MAH, NIM. 11620014
Subject
Fisika
Datestamp
2016-03-14 03:03:48
Abstract :
The analysis of Uranyl sulfate as a neutron irradiation target to calculation a neutron
multiplicity factor (keff). Uranium in sulfate compound in enrichment by 19.75 wt%
of U-235. This research aims to determine the design of AIR safe and has a a high
security level and influence of uranyl sulfate concentration of the criticality AHR.
Simulation analysis is done with using the package code MCNPX. The MCNPX code
used to make the design of AHR and a neutron multiplication factor (keff) calculation
to produce reactor critical AHR (keff=1). AHR design is modeled in the form of
cylindrical geometry is designed as close as possible to its original form . The output
of the simulation that produced a neutron multiplication factor (keff). From some
variation of the concentration of uranyl sulfate that has been done can be seen that the
concentration of uranyl sulfate produce reactor AHR critical (keff=1) is the
concentration of 215 g/L, with the value of keff = 0.99951 and standard deviation =
0.00060 (0.99951 ± 0.00060), At this concentration of uranyl sulfate solution
obtained height of 20.5 cm.
Keywords: AHR, keff, MCNPX, uranyl sulfate.