Xianan Du

Coupled neutronics–thermal–thermal expansion analysis of a heat pipe-cooled reactor using the SARAX code

Heat pipe cooled reactors are perceived as promising for providing power supply in remote grids owing to their compactness and safety properties. In this context, thermal expansion plays an important role in inducing sufficient negative reactivity during operation and accident co...

Multiphysics analysis of hydrogen kinetics and their effects in UZrHx-fueled reactors

Hydrogen kinetics within the Uranium–zirconium hydride (UZrH x ) fuel, including redistribution, dissociation, and permeation loss, can alter local moderating capability and material properties, thereby affecting core neutronics and safety characteristics. In this work, a hydroge...