Article ID Journal Published Year Pages File Type
298767 Nuclear Engineering and Design 2008 7 Pages PDF
Abstract

The purpose of this work was to evaluate the content of difficult to measure isotope 129I in the RBMK-1500 reactor fuel-to-clad gap and reactor main circulation circuit (MCC) coolant. To determine fission product (FP) release from the defective fuel, the methodology proposed by Lewis and Husain for the CANDU reactor primary coolant activity prediction was applied. The determined effective diffusion coefficient D′ = 1.2E−09 s−1 of iodine in the RBMK-1500 fuel is higher than the one evaluated for the CANDU fuel 6.8E−10 s−1. Results show that the method developed by Lewis and Husain can be applied for the RBMK-1500 fuel gap and reactor main circulation circuit coolant activity prediction.

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Physical Sciences and Engineering Energy Energy Engineering and Power Technology
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