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Nuclear ReactorsSurvey of Basic Concepts Engineer
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absorber absorption cross section approximation assembly Atomic Energy average boundary conditions buckling factor calculated capture Chapter constant control rod coolant cosh critical reactor cylindrical decay defined delayed neutrons designated determined diffusion length diffusion theory effective elastic scattering evaluated example experimental fast fission fast neutrons Fermi age Figure finite fission neutrons fission products fraction fuel elements geometry grad graphite heterogeneous reactors homogeneous reactor isotropic kernel kinetic energy lattice leakage lethargy mean free path method moderator monoergic multigroup natural uranium neutron absorption neutron flux neutron source neutron temperature neutrons produced noted nuclear reactor Nucleonics nucleus nuclides number of neutrons obtained one-group particle plane source point source prompt neutron radius ratio reaction reactivity reflector region represents resonance escape probability resonance integral scattering collisions sinh slab slowing-down density solution spatial spectrum spherical temperature thermal fission thermal neutron Thermal Reactor thermal utilization factor tion total number two-group theory values