
doi: 10.2172/4387966
A theoretical analysis of UO/sub 2/-- PuO/sub 2/ fueled, light-water- moderated lattice experiments has been performed to aid in establishing technical bases and design criteria for the utilization of plutonium bearing fuel in thermal power reactors. Results for UO/sub 2/ and Al-- Pu lattices are included in order to understand the effects due to uranium and plutonium separately. The problems involved in calculating high leakage critical experiments are discussed. Estimates of the effects of various approximations inherent in the theoretical methods and/or analysis procedures are included along with the consequence on the results of the correlation. Uncertainties in the measurements and the neutron crosssection data are related to uncertainties in the calculated values K/sub eff/ .The results of other studies which bear on evaluating the calculational methods are summarized. Areas which should be investigated in future analyses are also identified. (111 references) (auth)
Criticality, Uranium Dioxide, Reactivity, Plutonium Oxides, Fuel Elements, *Water Moderated Reactors-- Reactor Cores, N79100* --Reactors--Reactor Theory & Calculation, *Reactor Cores-- Reactor Kinetics, 530, *Thermal Reactors-- Reactor Cores, 620
Criticality, Uranium Dioxide, Reactivity, Plutonium Oxides, Fuel Elements, *Water Moderated Reactors-- Reactor Cores, N79100* --Reactors--Reactor Theory & Calculation, *Reactor Cores-- Reactor Kinetics, 530, *Thermal Reactors-- Reactor Cores, 620
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