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PRINCIPAL CONCEPTS OF REACTOR THEORY AND THE USES OF
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absorption cross-section angular approximation assumed asymptotic atoms average Boltzmann equation boundary conditions calculation cent chain reactor chapter coefficient compound nucleus computed control rod corresponding criticality factor decrease delayed neutrons denoted depends diffusion equation diffusion length escape probability experimental exponential expression extrapolation distance fast effect fast neutrons finite fission neutrons fission products formula fuel element function given gives grad graphite Hence increase inelastic scattering infinite kernel lattice lethargy material buckling mean free path measured medium method moderator multiplication factor natural uranium natural-uranium neutron density neutron distribution neutron energy neutron flux neutron temperature neutrons absorbed nuclear nuclei number of neutrons obtained particles Phys PICG quantity radius ratio reaction reflector region resonance absorption resonance escape resonance integral result scattering cross-section slowing-down solution spectrum spherical harmonics surface Table temperature term thermal neutrons thermal reactors thermal utilization tion trons unit velocity width zero