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Neutronic Analysis of Generic Heavy Water Research Reactor Core Parameters to Use Standard Hydride Fuel

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DOI: 10.4236/wjnst.2011.12008    5,051 Downloads   12,506 Views   Citations

ABSTRACT

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.

Conflicts of Interest

The authors declare no conflicts of interest.

Cite this paper

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.

References

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