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本文对我国自行设计的60万千瓦核电站在发生大破口失水事故时作用在堆内部件上的受力载荷、泄漏冷却剂的惯性冲击力和安全壳压力等进行了初步分析。讨论了破口裂开时间对受力载荷的影响。对饱和喷射阶段的惯性冲击力和如何防止喷射力对安全壳的破坏等问题也进行了探讨.
In this paper, a preliminary analysis is made on the force load, the inertial impact of the leaked coolant and the containment pressure on the self-designed 600 MW nuclear power station in the event of a large breakwater loss accident. The influence of breakage time on load is discussed. Inertia impact of saturated jet stage and how to prevent the destruction of jetting force on containment and other issues are also discussed.