Void fraction distribution characteristics in rod bundle with grid spacer is one of the important aspects in reactor thermal hydraulic characteristics research.

Volumetric expansion coefficient and compressibility of water and steam are important parameters usually applied in the reactor thermal hydraulic, heat transfer and engineering thermodynamics.

The PWR in-core temperature detection device, which is one of measures to ensure reactor safety operation, is to monitor and diagnose reactor thermal power output and in-core power distribution.