1-D Nuclear Reactor Slab Neutron Flux Analytical Solution
Version 1.0.0 (2.68 KB) by
Matthew
This code simulates the neutron flux and Keff for a 1-D slab reactor of various fuel compositions and slab lengths.
This code makes use of 1-D two group diffusion theory for a slab reactor to find the analytical solution for two fuel compositions and a user input length.
Cite As
Matthew (2026). 1-D Nuclear Reactor Slab Neutron Flux Analytical Solution (https://www.mathworks.com/matlabcentral/fileexchange/174075-1-d-nuclear-reactor-slab-neutron-flux-analytical-solution), MATLAB Central File Exchange. Retrieved .
MATLAB Release Compatibility
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R2024b
Compatible with any release
Platform Compatibility
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| Version | Published | Release Notes | |
|---|---|---|---|
| 1.0.0 |
