首页|堆芯筒体压力-温度(P-T)曲线的概率断裂力学分析研究

堆芯筒体压力-温度(P-T)曲线的概率断裂力学分析研究

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反应堆压力容器压力-温度曲线是核电厂正常运行的限值边界,保证了核能设备的运行安全.目前规范中给出了计算压力-温度曲线的方法,然而该方法得到的结果具有很高的保守性.本研究从概率断裂力学的角度,以高辐照区堆芯筒体为计算对象,开展了压力容器堆芯筒体压力-温度曲线的研究.研究结果指出:核电厂启堆过程、水压试验过程的风险很低,停堆过程中要关注降温速率;对于启堆过程、停堆过程和水压试验,结合概率分析结果提出了新的安全系数.
Probabilistic Fracture Mechanics Analysis of the Pressure-Tempera-ture Curve of the Core Beltline
The pressure-temperature curve of the reactor pressure vessel is the limit boundary for the normal operation of nuclear power plant,ensuring the safe operation of nuclear energy equipment.Now,the standard provides the method for calculating the pressure-temperature curve,but results obtained by this method have high conservatism.From the perspective of probabilistic fracture mechanics,and used the high irradiation zone of core beltline as the calculation case to study the pressure-temperature curve of the core beltline of pressure vessel.The study results indicate that the risk of the reactor heat-up and the hydro test process of nuclear power plant is very low,and attention should be paid to the cooling rate during the reactor cool-down.The new safety coefficients have been proposed based on the results of the probability analysis for the reactor heat-up,reactor cool-down,and hydro test.

probabilistic fracture mechanicspressure-temperature curvenuclear power plantbeltline

石凯凯、李政、刘青阳、艾红雷、张丽屏

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中国核动力研究设计院,先进核能技术全国重点实验室,四川 成都 610213

生态环境部核与辐射安全中心,北京 100042

概率断裂力学 压力-温度曲线 核电厂 堆芯筒体

2024

中国核电
中国原子能出版社

中国核电

影响因子:0.296
ISSN:1674-1617
年,卷(期):2024.17(5)