混合堆芯的热工水力设计是一项关系到核安全和可靠生产的重要内容。
Mixed core compatibility is one of important issues affecting the nuclear safety and the reliable generation of a nuclear Power Plant.
堆芯出口热气混合实验用于测量和分析该混流结构的混合性能及其阻力特性。
A hot gas mixing experiment of outlet of HTR-PM reactor core was proposed to measure and analyze the actual mixing performance and resistance property of this mixing structure.
堆芯出口热气混合实验用于测量和分析该混流结构的混合性能及其阻力特性。
A hot gas mixing experiment of outlet of HTR-PM reactor core was proposed to measure and analyze the actual mixing performance and resistance property of this mixing structure.
应用推荐