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针对核反应堆专设安全设施试验间隔期的优化,以传统的专设安全设施组成设备平均可用度模型为基础,提出采用较少假设近似并考虑设备在备用、试验和检修3阶段状态关联的可用度模型。改进模型比原模型具有更为广泛的适用性,对大型复杂系统、精度要求比较高的分析计算具有优势。将该模型用于核反应堆余热排出系统试验间隔期的确定,结果能够为核反应堆专设安全设施的使用管理和维修决策提供参考。
Aiming at the optimization of the test interval of the dedicated safety facilities of the nuclear reactor, based on the average equipment availability model of the dedicated safety equipment, the availability of less hypothetical approximations and consideration of the state correlation of the equipment in the standby, test and maintenance phases is proposed. model. The improved model has a wider range of applicability than the original model, which has advantages for the analysis of large and complex systems and high accuracy requirements. The model was used to determine the test interval of the residual heat removal system of nuclear reactor. The results can provide references for the management and maintenance decision-making of the safety facilities dedicated to nuclear reactors.