Development of a Predictor-Corrector Quasi-Static Transient Fission Matrix combination method for the neutronics transient simulation

Author:

He DonghaoORCID,Li Yuehang,Pan Qingquan,Liu XiaojingORCID

Publisher

Elsevier BV

Reference56 articles.

1. Deterministic Time-Dependent Neutron Transport Benchmark Without Spatial Homogenization (C5G7-TD);Boyarinov,2016

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4. Theory and applications of the fission matrix method for continuous-energy Monte Carlo;Carney;Ann. Nucl. Energy,2014

5. A nonoverlapping local/global iterative method with 2-D/1-d fusion transport kernel and p-CMFD wrapper for transient reactor analysis;Cho;Ann. Nucl. Energy,2015

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