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NEUTRON SOURCES AND DETECTION
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absorbed absorption Answer assumed atomic average boundary calculate called cell chamber coefficient collision concentration condition considered constant containment coolant cooling core cost counter critical cross-section decay delayed density determined diffusion distribution dose effect Electric electron element energy engineering enrichment equation example factor fast neutrons Figure fission fission neutrons flow flux fuel function gamma geometry given gives heat height heterogeneous homogeneous important increase interest lead length loss mass materials maximum measuring method moderator noted nuclear nucleus obtained operation particle photon plant possible pressure primary probability problem production radiation radioactive radius reaction reactor reflector region removal resonance respectively result Safety scattering separation shield slow solution solved steam surface Table temperature theory thermal neutron thickness transfer types unit uranium volume