Consider a critical bare slab thermal reactor 2m thick fuelled with 235U and moderated by graphite....

 

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Consider a critical bare slab thermal reactor 2m thick fuelled with 235U and moderated by graphite. The neutron diffusion length in the graphite is 0.016m. Notice that the scattering is mainly caused in graphite but ignored in the uranium. Using one-group theory, you are required to: (1) Calculate the geometric buckling of the reactor; (2) Calculate the neutron leakage probability of the reactor; (3) Consider the slab reactor reflected by an infinite reflector of graphite, calculate the critical size of the reactor core, and the reflector saving compared to the original bare slab reactor. (Note that when x→ +∞o, coth x→ 1). Consider a critical bare slab thermal reactor 2m thick fuelled with 235U and moderated by graphite. The neutron diffusion length in the graphite is 0.016m. Notice that the scattering is mainly caused in graphite but ignored in the uranium. Using one-group theory, you are required to: (1) Calculate the geometric buckling of the reactor; (2) Calculate the neutron leakage probability of the reactor; (3) Consider the slab reactor reflected by an infinite reflector of graphite, calculate the critical size of the reactor core, and the reflector saving compared to the original bare slab reactor. (Note that when x→ +∞o, coth x→ 1).

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