Monte Carlo criticality-mode systems and methods for...

Data processing: structural design – modeling – simulation – and em – Simulating nonelectrical device or system

Reexamination Certificate

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C703S002000, C703S007000, C250S428000, C250S43200R

Reexamination Certificate

active

10191620

ABSTRACT:
A method for simulating three-dimensional spatial distribution of neutron and gamma fluences in a nuclear reactor includes, in an exemplary embodiment, generating a detailed geometric configuration of a nuclear reactor core and surrounding components, generating detailed fuel composition and concentration distribution, and calculating three-dimensional nuclide concentrations for the fuel rods and the water surrounding the fuel rods using the generated geometric configuration and generation fuel composition and concentration distributions. The method also includes calculating neutron and gamma fluxes using a Monte Carlo radiation transport criticality mode methodology, and generating a neutron and gamma fluence map for predetermined areas of the reactor.

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