Publication | Closed Access
An Approximate Method for Treating Neutron Slowing Down
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Citations
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References
1960
Year
EngineeringNuclear PhysicsNuclear DataReactor PhysicsReactor AnalysisTreating NeutronCross SectionsNuclear MaterialsNuclear DecayNuclear ReactorsIsotropic Flux φPhysicsNuclear TheoryNeutron SourceApproximate RelationNeutron TransportNuclear EngineeringNatural SciencesNeutron Scattering
The slowing down density, q, of neutrons in a reactor may be decomposed into a sum of parts due to various nuclear specieshaving corresponding scattering cross sections µs1, µs2, ···. An approximate relation between qi and isotropic flux φ(u) (where u is the lethargy) is proposed..The values of γi and ξi are derived and interpreted.
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