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Forums
Engineering
Nuclear Engineering
Neutron Flux in a sub-critical reactor
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[QUOTE="Oxlade, post: 5610443, member: 607777"] Hi everyone, I am supposed to derive the neutron flux equation provided for region A of my reactor. Just wondering if anyone can help me out since I stuck on the derivation for [1/r - 1/R2]; S/4πD aspect is very similar to a solving the constant for a point source spherical reactor Here is my reactor diagram consisting of nested spheres (sorry, this is my first time posting): Sphere 1 --> Lead target with radius of R0 (Target-region) Sphere 2 --> Actinide Fuel surrounding lead target; has outer radius of R1 (A-region) Sphere 3 --> Reflector surrounding the fuel with outer radius of R2 (E-region) Neutron Flux vanished at R2 and the flux at A-region is given as: Φ(r) = S/4πD [1/r - 1/R2]My attempts at deriving this equation always leaves me with exponential terms if I'm assuming I'm solving the diffusion equation for a finite spherical reactor with a point source. Can anyone help me? [/QUOTE]
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Nuclear Engineering
Neutron Flux in a sub-critical reactor
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