Method for the calculation of neutrons - and gamma flow in a nuclear reactor

摘要

A method for simulating three-dimensional spatial distribution of neutrons - and gamma flux densities in a nuclear reactor, in an exemplary embodiment, generating a detailed geometrical configuration of a reactor core and the surrounding components, generate fuel composition - in greater detail and distribution of concentration and calculating three-dimensional nuclide concentrations for the fuel rods and the water surrounding the fuel rods with the use of the generated geometric configuration and of the generated fuel composition - and distributions. The method also contains the calculation of neutrons - and γ with the use of the inner ends of the wings - of a monte carlo radiation transport - criticism alite uct - method and generating a neutrons - and gamma flux density map for predetermined regions of the reactor.