Nuclear Science and Engineering / Volume 6 / Number 2 / August 1959 / Pages 100-118
Technical Paper / dx.doi.org/10.13182/NSE59-A25640
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The various conventions and definitions of thermal and resonance flux are discussed. Measurements of the thermal neutron cross sections, resonance integrals, and reactor cross sections of the following nuclides are critically reviewed: Th232, Th233, Pa233, U233, U234, U235, U236, U238, U239, Np239, Pu239, Pu240, Pu241, and Pu242.