Article ID Journal Published Year Pages File Type
6758647 Nuclear Engineering and Design 2018 9 Pages PDF
Abstract
This new instrumentation was successfully tested and allows the first-time measurement, under BWR operating conditions, of relevant two-phase flow parameters such as the local void fraction in the steam core, the local drop/steam velocity, the volumetric interfacial area, the drop collision frequency and the assessment of drop size distribution during BWR steady-state and transient operations.
Related Topics
Physical Sciences and Engineering Energy Energy Engineering and Power Technology
Authors
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