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- W300366275 abstract "Systematic procedures have been devised and applied to evaluate core design and fuel management strategies for improving uranium utilization in Pressurized Water Reactors operated on a once-through fuel cycle. A principal objective has been the evaluation of suggested improvements on a self-consistent basis, allowing for concurrent changes in dependent variables such as core leakage and batch power histories, which might otherwise obscure the sometimes subtle effects of interest. Two levels of evaluation have been devised: a simple but accurate analytic model based on the observed linear variations in assembly reactivity as a function of burnup; and a numerical approach, embodied in a computer program, which relaxes this assumption and combines it with empirical prescriptions for assembly (or batch) power as a function of reactivity, and core leakage as a function of peripheral assembly power. State-of-the-art physics methods, such as PDQ-7, were used to verify and supplement these techniques." @default.
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- W300366275 date "1981-01-01" @default.
- W300366275 modified "2023-09-24" @default.
- W300366275 title "Analysis of strategies for improving uranium utilization in pressurized water reactors. Annual technical progress report for FY 1980" @default.
- W300366275 hasPublicationYear "1981" @default.
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