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Verification of 235U by using MCNP code with comparison MGAU analysis software for the enriched uranium (4.462%) in different distance |
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PP: 31-35 |
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Author(s) |
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S. A. Makhlouf,
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Abstract |
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| The verification method was based on non-Destructive (ND) measurements of gamma radiation emitted from nuclear material. Some of the parameters which affect NM mass estimation were calculated using Monte Carlo method. The present procedure could be very useful for safeguards purposes. Also, the verification by (ND) based on MGAU With comparison tow method. All the obtained results based on MCNP5 were in agreement with the declared values within the estimated relative accuracy (-0.319, -0.783 and -1.312%) and relative precision (1.78, 1.74 and 1.8%) for three different distances (14, 16 and 18.3), respectively. The relative accuracy obtained from MGAU were (-0.695, 1.748 and 1.277%) and relative precision (2.96, 2.78 and 3.065%) for this different distances, respectively. But the relative precision is relatively large in case depleted uranium. It was supposed to be due to the short life time of measurements. Of all the above we can say that, The Monte Carlo method fits the measurement conditions of the inspector and also the conditions for normal measurements are therefore better than MGAU method.
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