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http://dx.doi.org/10.5516/NET.01.2014.712

NUCLEAR DATA UNCERTAINTY PROPAGATION FOR A TYPICAL PWR FUEL ASSEMBLY WITH BURNUP  

Rochman, D. (Nuclear Research and Consultancy Group NRG, Petten)
Sciolla, C.M. (Nuclear Research and Consultancy Group NRG, Petten)
Publication Information
Nuclear Engineering and Technology / v.46, no.3, 2014 , pp. 353-362 More about this Journal
Abstract
The effects of nuclear data uncertainties are studied on a typical PWR fuel assembly model in the framework of the OECD Nuclear Energy Agency UAM (Uncertainty Analysis in Modeling) expert working group. The "Fast Total Monte Carlo" method is applied on a model for the Monte Carlo transport and burnup code SERPENT. Uncertainties on $k_{\infty}$, reaction rates, two-group cross sections, inventory and local pin power density during burnup are obtained, due to transport cross sections for the actinides and fission products, fission yields and thermal scattering data.
Keywords
Uncertainty; Nuclear Data; Fast TMC;
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