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A neutron transport solver for 2-D, 2-energy-group neutron noise problems is presented. The simulator allows to determine: 1) the static neutron flux associated with a critical system; 2) the neutron noise in the frequency domain, according to a prescribed perturbation of the critical system. The perturbation is modeled as stationary fluctuations of the macroscopic nuclear cross-sections. The solution algorithm is based on a diamond finite difference scheme, discrete ordinates method, and it is accelerated using a diffusion synthetic acceleration technique. The solver is tested on 2-D homogeneous and heterogeneous systems with a localized neutron noise source. Its convergence is analyzed and compared to the case without acceleration.
Reactor neutron noise, discrete ordinates, diffusion synthetic acceleration, convergence analysis
Reactor neutron noise, discrete ordinates, diffusion synthetic acceleration, convergence analysis
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