Fuel rod analysis program transient (FRAPTRAN) code was used to study the fuel rod performance during a postulated large break loss of coolant accident (LBLOCA) in Maanshan nuclear power plant (NPP). Previous transient results from thermal hydraulic code, TRACE, with the same LBLOCA scenario, were used as input boundary conditions for FRAPTRAN. The simulation results showed that the peak claddi...

This paper describes a multi-scale modeling approach to compute the large-strain deformation of zirconium alloy cladding, which is of interest to the study of fuel rod behaviors in transient and accident conditions. A Visco-Plastic Self-Consistent (VPSC) polycrystal plasticity model representing polycrystals by weighted orientations of single crystals has been implemented as the constitutive la...

A quenching experiment is performed to investigate the heat transfer characteristics and cooling performance of CrAl-coated Zircaloy (Zr) cladding in a water flow. The Zr one accident tolerant fuels for light reactors. uncoated also used this comparison. This simulates reflood fuel rod during loss coolant (LOCA) nuclear power plant. test conditions were determined represent peak temperature, su...

The Ornstein-Zernike (OZ) equations [1] can be used to find probability distributions of atoms in fluid states where the primary unknowns are the radial pair correlation function and the direct correlation function. In order to specify conditions of the state, certain parameters such as density and temperature are chosen. While one can find a single solution to the OZ equations corresponding to...

Post-LOCA prediction is of safety significance to NPP, but requires a processing coverage non-linearity, both short and long-term memory, multiple system parameters. To enable an ability promotion previous LOCA models, new gate function called zigmoid introduced embedded the traditional long short-term memory (LSTM) model. The newly constructed zigmoid-based LSTM (zLSTM) amplifies gradient at f...

The safety performance of nuclear power plants (NPPs) is a very important factor in evaluating energy sustainability. Safety analysis passive and active systems have positive influence on reactor transient mitigation. One the common transients primary coolant leg rupture. This study focused guillotine large break loss (LB-LOCA) one vessels, which cold rupture occurred, after establishment stead...