摘要
核电站在启停堆过程中,需要将压力、温度控制在压力温度限值曲线(P—T曲线)所规定的范围内。在P—T曲线的制定过程中,涉及与温度相关的参数包括升降温速率、一回路流体温度和裂纹前缘温度。对比分析最新版ASME(American Society of Mechanical Engineers)规范和RCCM(Design and Construction Rules for Mechanical Components for PWRNuclear Islands)规范在P—T曲线计算方面的差异,基于2007版RCCM规范提出新的P—T曲线计算流程,通过数值算例分别研究温度相关参数对基于ASME规范和基于RCCM规范得到的P—T曲线的影响。数值分析显示温度相关参数的影响与所采用的标准、升降温工况等因素有关。研究结果可供P—T曲线工程计算参考,有助于核电站安全、可靠的使用反应堆压力容器。
During nuclear power plant(NPP) heat up and cool down processes,pressure and temperature in a Reactor Pressure Vessel(RPV) should be kept under the pressure-temperature(P—T) limit curve.For the P—T limit curve calculation three temperature-related parameters are required,including the fluid temperature of primary loop,the temperature at crack-tip and the temperature changing rate.The comparison of the latest versions of the RCCM(Design and Construction Rules for Mechanical Components for PWR Nuclear Islands) code and the ASEM(American Society of Mechanical Engineers) code is performed.A new P—T limit curve calculation procedure based on the Ver.2007 RCCM code is proposed.Furthermore,the effects of the temperature-related parameters on the P—T limit curves are studied.The result shows that the effect of the temperature-related parameters depends on the adopted standards,the heat up and cool down processes and other factors.The conclusion can be used to calculate the P—T limit curve.
出处
《机械强度》
CAS
CSCD
北大核心
2013年第4期454-459,共6页
Journal of Mechanical Strength
基金
国家863课题项目(2012AA050901)
国家自然科学基金项目(51275338)资助
江苏省自然科学基金(BK2009560)
苏州市(金阊区)2011年度科技计划项目的资助~~