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http://dx.doi.org/10.1016/j.net.2014.11.002

NEUTRONICS INVESTIGATION OF CANADA DEUTERIUM URANIUM 6 REACTOR FUELED (TRANSURANICeTH) O2 USING A COMPUTATIONAL METHOD  

GHOLAMZADEH, ZOHREH (Reactor Research School, Nuclear Science and Technology Research Institute)
MIRVAKILI, SEYED MOHAMMAD (Reactor Research School, Nuclear Science and Technology Research Institute)
KHALAFI, HOSSEIN (Reactor Research School, Nuclear Science and Technology Research Institute)
Publication Information
Nuclear Engineering and Technology / v.47, no.1, 2015 , pp. 85-93 More about this Journal
Abstract
Background: $^{241}Am$, $^{243}Am$, and $^{237}Np$ isotopes are among the most radiotoxic components of spent nuclear fuel. Recently, researchers have planned different incineration scenarios for the highly radiotoxic elements of nuclear waste in critical reactors. Computational methods are widely used to predict burnup rates of such nuclear wastes that are used under fuel matrixes in critical reactors. Methods: In this work, the Monte Carlo N-particle transport code was used to calculate the neutronic behavior of a transuranic (TRU)-bearing CANada Deuterium Uranium 6 reactor. Results: The computational data showed that the 1.0% TRU-containing thorium-based fuel matrix presents higher proliferation resistance and TRU depletion rate than the other investigated fuel Matrixes. The fuel matrix includes higher negative temperature reactivity coefficients as well. Conclusion: The investigated thorium-based fuel matrix can be successfully used to decrease the production of highly radiotoxic isotopes.
Keywords
$^{241/243}Am$ and $^{237}Np$ Incineration; CANada Deuterium Uranium 6 Reactor; Neutronic Evaluation; Transuranic-Containing Fuel Matrix;
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