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A Hybrid Approach to the Neutron Transport k-Eigenvalue Problem using NDA-based Algorithms

By Jeffrey A. Willert, C. T. Kelley, D. A. Knoll and H. Park


In order to provide more physically accurate solutions to the neutron transport equation it has become increasingly popular to use Monte Carlo simulation to model nuclear reactor dynamics. These Monte Carlo methods can be extremely expensive, so we turn to a class of methods known as hybrid methods, which combine known deterministic and stochastic techniques to solve the transport equation. In our work, we show that we can simulate the action of a transport sweep using a Monte Carlo simulation in order to solve the k-eigenvalue problem. We’ll accelerate the solution using nonlinear diffusion acceleration (NDA) as in [1,2]. Our work extends the results in [1] to use Monte Carlo simulation as the high-order solver

Topics: Key Words, Eigenvalue Calculation, Nonlinear Acceleration, Hybrid Methods
Year: 2013
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