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2015•Annals of Nuclear EnergyRequires access

Burnup-dependent core neutronics analysis of plate-type research reactor using deterministic and stochastic methods

Shichang Liu, Guanbo Wang, Jingang Liang, Gaochen Wu, Kan Wang

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Key concepts: Burnup, Neutron transport, Monte Carlo method, Research reactor, Nuclear engineering, Computer science, Nuclear reactor core, Neutron

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