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What Pile Theory Is and What It Involves
A Survey of Pile Types and Problems
The SlowingDown of Neutrons Part 1
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absorption cross section air channels aluminum approximation assembly atoms average boundary conditions Brookhaven calculations chain reaction channel area collision considered control rods coolant core critical buckling critical size cubical pile cylindrical decrease delayed neutrons diffusion length effect elastic collisions equation excess reactivity experimental fast fission fast neutrons fission neutrons fissionable material flux distribution foil formula fraction fuel function given graphite heavy water heterogeneous increase indium infinite jacket keff lattice spacing leakage lecture maximum mean free path migration area moderator multiplication factor natural uranium neutron density neutron flux neutrons absorbed neutrons produced Nuclear Reactor nuclei Nucleonics number of neutrons Oak Ridge obtained one-group operation pile theory problem quantity radiative capture reflector saving resonance absorption resonance escape probability rod radius scattering slab slowing-down density Table temperature thermal energies thermal neutron flux thermal neutrons thermal utilization thickness unity uranium rod uranium-graphite velocity volume ratio