Roots and Coefficients from the Integral Solution of the Reactor Kinetic Equations Applicable to Uranium-235 Fueled, Heavy Water Moderated Reactors

Joseph S. Crudele; Richard A. Danofsky

doi:dx.doi.org/10.13182/NSE71-A22381

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Home / Publications / Journals / Nuclear Science and Engineering / Volume 46 / Number 3

Roots and Coefficients from the Integral Solution of the Reactor Kinetic Equations Applicable to Uranium-235 Fueled, Heavy Water Moderated Reactors

Joseph S. Crudele, Richard A. Danofsky

Nuclear Science and Engineering / Volume 46 / Number 3 / December 1971 / Pages 425-427

Technical Note / dx.doi.org/10.13182/NSE71-A22381

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The characteristic parameters necessary to describe the kinetic behavior of D₂O moderated reactors have been calculated for various prompt-neutron lifetimes. Comparison is made of the reactor response to reactivity changes when evaluated using fast-fission and thermal-fission delayed-neutron-group constants combined with D₂O photoneutron constants.