首页> 美国政府科技报告 >ANALYSIS OF ACCIDENTS IN THE PRIMARY CIRCUIT OF AN ATOMIC ELECTRIC POWER PLANT WITH WATER -MODERATED WATER-COOLED REACTORS DURING PIPE RUPTURES
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ANALYSIS OF ACCIDENTS IN THE PRIMARY CIRCUIT OF AN ATOMIC ELECTRIC POWER PLANT WITH WATER -MODERATED WATER-COOLED REACTORS DURING PIPE RUPTURES

机译:管道破裂过程中水冷却水冷却反应堆原子电厂初级电路事故分析

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摘要

An analysis is made of accidents connected with the development of looseness in elements of the primary circuit of an atomic electric power plant with water-moderated water-cooled reactors. Data are presented which generalize experimental investigations to determine the critical hot-water flow rates. On the basis of a multiregional model of the primary circuit, equations of energy and mass conservation and an equation of state are given which permit determining the character of the change of the coolant para¬meters when a leak forms.

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