Burnup simulations of different fuel grades using the MCNPX Monte Carlo code

Burnup simulations of different fuel grades using the MCNPX Monte Carlo code

Global energy problems range from the increasing cost of fuel to the unequal distribution of energy resources and the potential climate change resulting from the burning of fossil fuels. A sustainable nuclear energy would augment the current world energy supply and serve as a reliable futur...

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Bibliographic Details
Main Authors: Asah-Opoku Fiifi, Liang Zhihua, Huque Ziaul, Kommalapati Raghava R.
Format: Article
Language:English
Published: VINCA Institute of Nuclear Sciences 2014-01-01
Series:Nuclear Technology and Radiation Protection
Subjects:
MCNPX code
burnup calculation
criticality calculation
radionuclide inventory
Online Access:http://www.doiserbia.nb.rs/img/doi/1451-3994/2014/1451-39941404259A.pdf

Internet

http://www.doiserbia.nb.rs/img/doi/1451-3994/2014/1451-39941404259A.pdf

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