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Shield Design Criteria and Procedures
Sources of Neutrons and Gamma Rays
7 other sections not shown
Air-scattered albedo angular distribution approximation assumed Atomic attenuation coefficient attenuation kernel axis bremsstrahlung capture Capture-gamma-ray spectrum collision component Compton scattering computed concrete cosine crew compartment curve cylindrical duct decay density detector dose buildup factors effect emitted experimental exponential Exponential integrals fast-neutron dose fission products function Gamma gamma-ray geometry given Goldstein hydrogen incident inelastic scattering integral LTSF mean free paths measured medium moments method Monte Carlo method neutron energy neutron flux normal Nuclear nucleus Oak Ridge National obtained ORNL parameters penetration photons Phys radiation radiative capture ray analysis reaction Reactor Shielding relaxation length removal cross section Ridge National Laboratory separation distance shield design Shielding Facility shown in Fig single-scattering slab shield solid angle source angle source energies source strength source-detector spectra surface source Table tank thermal thermal-neutron thickness tion transmission tron unit USAEC Report values voids volume source