摘要
The nuclide depletion calculation is of great significance in the design and research of the reactor core scheme.The change of nuclide content can be described by the Bateman equation[1],and the kernel of reactor burnup calculation is the solution of Bateman equation.The classic calculation program for nuclide depletion has procedures such as ORIGEN.Since the half-life values of nuclide are widely distributed,the norm of fuel consumption coefficient matrix of the nuclides is very large,so it is difficult to numerically solve the equation.
