1961•Journal of Nuclear Energy Part B Reactor TechnologyRequires access

A Method of Predicting the Critical Mass and Neutron Flux Distribution of a Reactor by Use of a Physical Model

Vladimir Dmitrievskii, I. S. Grigor’ev

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Key concepts: Fissile material, Neutron flux, Neutron cross section, Neutron, Nuclear engineering, Neutron poison, Neutron temperature, Nuclear physics

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