Nuclear-data uncertainty propagations in burnup calculation for the PWR assembly
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DOI: 10.1016/j.anucene.2016.09.037
Abstract: Abstract In this paper, our home-developed lattice code NECP-CACTI has been implemented into our UNICORN code to perform sensitivity and uncertainty analysis for the lattice calculations. The verified multigroup cross-section perturbation model and methods of… read more here.
Keywords: burnup calculation; uncertainty; calculation; sensitivity uncertainty ... See more keywords
Comparative analysis of coupling schemes of Monte Carlo burnup calculation in RMC
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DOI: 10.1016/j.anucene.2019.107024
Abstract: Abstract As wrapping tools for coupling Monte Carlo (MC) neutron transport code with depletion solver, four different coupling schemes are implemented in Reactor Monte Carlo Code (RMC) developed at Tsinghua University, and verified in two… read more here.
Keywords: comparative analysis; burnup calculation; monte carlo; coupling schemes ... See more keywords