Journal of Nuclear Science and Technology · 1966 · 19 citations · 2 references
EngineeringPhysicsNuclear PhysicsTransportTransport PhenomenaBoltzmann Transport EquationEigenvalue ProblemsNeutron ScatteringNeutron TransportNeutron Transport TheorySpectral TheoryEigenvalue ComputationEigenvalue Neutron Transport ProblemsEigenvaluesEnergy EigenvaluesNeutron Transport Equation
The eigenvalue problem of the monoenergetic neutron transport operator is studied mathematically under the assumptions of homogeneity and boundedness of the medium and of isotropy of scattering. It is shown that the spectrum involves a countable infinity of real eigenvalues with an accumulation point at minus infinity. Each eigenvalue has a finite multiplicity.
2
<i>An Introduction to Transport Theory</i>
G. Milton Wing, George H. Weiss · Physics Today · 1963 · 283 citations
Engineering, Mathematics, Physics +10