Author(s)

Saman Tashakor, Farshid Javidkia, Mehdi Hashemi-Tilehnoee

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Department of Engineering, Islamic Azad University, Aliabad Katoul Branch, Aliabad Katoul, Golestan, Iran.

This research presents neutronic calculations for heavy water research reactor core substituting hydride fuel for uranium dioxide fuel. The aim of this research is feasibility analysis of reactor utilization with its original design using a new proposed fuel and changing the coolant and moderator circuit to light water. The required group constants for the CITATION code will be calculated using WIMSD-4 code. Neutronic calculations such as multiplication factors, radial and axial power peaking factor and fuel burn-up calculations are carried out by the CITATION code.

WIMSD-4, CITATION, Hydride Fuel, Research Reactor, Neutronic Analysis

S. Tashakor, F. Javidkia and M. Hashemi-Tilehnoee, "Neutronic Analysis of Generic Heavy Water Research Reactor Core Parameters to Use Standard Hydride Fuel," World Journal of Nuclear Science and Technology, Vol. 1 No. 2, 2011, pp. 46-49. doi: 10.4236/wjnst.2011.12008.