【摘 要】
：
反应堆压力容器钢(PRV)作为压水堆核电厂中唯一不可更换的关键核心设备,是防止核电厂放射性泄漏的最主要屏障,其使用寿命决定了核电厂的使用寿命,从而影响了核电厂的经济性和
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反应堆压力容器钢(PRV)作为压水堆核电厂中唯一不可更换的关键核心设备,是防止核电厂放射性泄漏的最主要屏障,其使用寿命决定了核电厂的使用寿命,从而影响了核电厂的经济性和安全性。由于长期受高温、高压、高剂量快中子辐照,PRV失效机理主要包括辐照脆化、热老化、疲劳老化、腐蚀及应力腐蚀等。利用Metropolis蒙特卡罗方法和分子动力学模拟了热老化引起的压力容器模型钢——FeMnNiCu合金中4种不同晶界{210}、{310}、{410}和{510}上溶质原子的偏聚行为和基体内沉淀物析出,分
As the key non-replaceable core equipment of PWR nuclear power plant, PRV is the most important barrier to prevent radioactive leakage of nuclear power plant. Its service life determines the service life of nuclear power plant, which affects the Economic and security. Due to long-term high-temperature, high-pressure, high-dose fast neutron irradiation, PRV failure mechanisms include radiation embrittlement, thermal aging, fatigue aging, corrosion and stress corrosion. The Metropolis Monte Carlo method and molecular dynamics simulation were used to simulate the thermal aging-induced partial pressure of solute atoms in the {210}, {310}, {410} and {510} of the pressure vessel model steel-FeMnNiCu alloy Poly act and sediment precipitation in the matrix, points
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