Acceptance report on advanced analysis model and method of nuclear fuel element capability
This project focused on the domestic nuclear fuel technology capacity shortcomings and international research hotspots, and the basic scientific research was carried out, which includes two-phase turbulent mixing in special-shaped channels, grid cross-flow mixing and interface transport process with two phases, and capability degradation mechanism of fuel rod elements. The rod bundle CHF prediction method and high-precision capability prediction model with independent intellectual property rights were built, breaking the monopoly of foreign countries in the nuclear fuel element design. The completed tasks in the project include: The development of high-precision measurement technology for phase characteristics in the complex special-shaped channels, and the research on phase distribution characteristics of rod bundles. The establishment and validation of the high-precision subchannel analysis method. Experimental study of the CHF influence mechanism on cold wall and rod bending, CFD thermal capability analysis of rod bending, CHF engineering experimental study on high temperature and high pressure grid-rod bundle, the development of wide-range multi-parameter CHF relationship and the research on CHF prediction mechanism model in complex special-shaped channel. The research on cladding irradiation test technology and irradiation capability detection technology under severe conditions has been completed. The model study of irradiation creep, hydride distribution and its influence on capability of zirconium alloy was completed, and the irradiated CZ model of creep and fatigue was established. This report elaborated the research content and technical validation process in detail.
Keywords: nuclear fuel element, two-phase distribution, high-precision subchannel code, rod bending, CHF, zirconium alloy model
