Calculation of power density distribution in miniature neutron source detector using the MTR_PC V2.6 code package

摘要

Spatial power distribution for the miniature neutron source detector (MNSR) has been calculated and presented as a function of the three coordinates. Accordingly, the MNSR Safety Analysis Report will be amended with the obtained information. The spatial power distribution has shown a maximum value for power density attained in the MNSR and reaches 3.24 w/cm(3), located near the core center in case where the control rod is fully withdrawn. The effect of the control rod position on such power space-distribution in all 3-axis and various location of the control rod in the core were analyzed. Total, axial and radial peak power factors have been calculated. Their values were 1.27, 1.14 and 1.116, respectively. The Argentinean MTR_PC V2.6 code package was installed and utilized for various applications, especially, neutronics calculations for nuclear research reactors. Finally, the package was verified and utilized it through the calculations of both delayed neutron fraction and the prompt neutron generation time for the MNSR. The obtained values for these two parameters were 7.8673E-03 and 8.1534E-05 s, respectively. These parameters were calculated using the core calculation code CITVAP i.e. CITATION, having the microscopic cross-section library obtained by the code BORGES based on the cell calculation WIMS code. The presented results are in a very close agreement with the published results.