The Effects of Refolding and Rewetting of Vertical Nuclear Fuel Bundle with Jet Impingements in Nuclear Reactors: A Review

摘要

Rewetting is very important content with thermal control for the safety of nuclear reactors during Loss of Coolant Accident (LOCA), also in manufacturing industries for controlling high temperature, and in micro-electric cooling for electronic systems thermal control. The limiting factor in heat removal in engineering systems involving liquid heat transfer is the boiling crisis. The boiling crisis is especially important in the field of nuclear engineering, as it is one of the main limits on the power extracted per unit volume for both Pressurized Water Reactors (PWR) and Boiling Water Reactors (BWR)[1]. Consequently, accurate knowledge of the rewetting is necessary for accurate and enhanced control of the quenching process. The boiling heat transfer regime plays an important role in rapid cooling applications. However, because of its complex and unsteady behavior, it has been historically the least studied. Due to increasing demand for the utility of rewetting in industry, researchers and scientists have carried out with analysis and experiments to study the rewetting phenomena. The following section reports the historical observation on the reflooding and rewetting mechanism. The motivational research gap from the present survey is also included in this chapter.