Two successive stages of the control of a beyond-design basis accident with de-energization of an RBMK reactor together with multiple equipment failures are analyzed: depressurization of the circulation loop and restoration of reactor cooldown with cold water as the reactor subsequently warms up. The factors affecting the pressure surge in the circulation loop on restoration of reactor cooling as the reactor heats up are examined. It is shown that the sequence of control actions and the employed equipment are effective from the standpoint of the possibility of overpressurization of the channel tubes and the reactor space. The state of the channel tubes and the reactor space in the presence of arising deformation loads was analyzed using an experimentally determined criterion for the acceptability (integrity) of a channel tube.

中文翻译：

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电站机组长期断电过程中RBMK物理安全屏障的完整性评估

对 RBMK 反应堆断电和多个设备故障的超设计基准事故控制的两个连续阶段进行了分析：循环回路降压和反应堆随后升温时用冷水恢复反应堆冷却。研究了在反应堆加热时影响反应堆冷却恢复的循环回路中的压力波动的因素。结果表明，从通道管和反应器空间过压的可能性的角度来看，控制动作的顺序和所采用的设备是有效的。使用实验确定的通道管可接受性（完整性）标准分析通道管和反应器空间在出现变形载荷时的状态。