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REACTOR CORE CONSIDERATIONS
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absorption cross-section approximately assumed attenuation beta beta decay coefficient of reactivity collision Compton effect concentration consideration considered control rods core critical mass decay decrease delayed neutron density detector dimensions effect elastic emitted enrichment factor fast neutrons fission chambers fission neutrons fission products fissionable material fluid flux distribution flux level fuel elements fuel rods gammas gas molecules geometric given heat Hence higher energies homogeneous increase inelastic inelastic collision interaction interface inverse multiplication curve isotopes kinetic energy leakage loading step macroscopic cross-section mass number moderator neutron absorption neutron balance relations neutron energy neutron flux neutron population neutrons absorbed Nuclear Reactor nuclei number of neutrons one-speed particle peak photons portion power level probability proportional ratio reac reduced reflector regulating rod resonance absorption safety rod samarium scattering shield shut-down slowing-down structure term thermal neutrons thermal range thermal reactor tion type of reactor unit path length unit volume uranium velocity xenon zero