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采用超临界水堆堆芯三维核热耦合瞬态性能分析方法,研究中国百万千瓦级超临界水堆(CSR1000)在控制棒弹出堆芯、控制棒失控抽出等典型瞬态过程中堆芯的瞬态性能。堆芯三维瞬态分析表明:控制棒弹出堆芯事故过程中燃料最大包壳壁面温度峰值低于事故安全限值(1260℃),控制棒失控抽出瞬态过程中燃料最大包壳壁面温度峰值低于瞬态安全限值(850℃)。燃料温度和水密度的显著反应性反馈以及必要的保护停堆措施,能够保证CSR1000堆芯在典型瞬态过程中的安全性能。
The three-dimensional nuclear thermal coupling transient performance analysis method of a supercritical water reactor core was used to study the characteristics of core of a Chinese kilowatt-class supercritical water reactor (CSR1000) during the typical transient process of ejecting the control rod, losing control rod, Transient performance. The three-dimensional transient analysis of the core shows that the peak temperature of the maximum cladding wall temperature below the accidental safety limit (1260 ℃) during the control rod pop-up event and the peak peak temperature of the fuel cladding wall during the uncontrolled withdrawal of the control rod Transient safety limit (850 ℃). The significant reactivity feedback of the fuel temperature and water density together with the necessary protection shutdown measures ensure the CSR1000 core’s safety during typical transient conditions.