【作者】 李剑； 李宇； 陈俊； 申爱景； 杨燕华；

【Author】 LI Jian;LI Yu;CHEN Jun;SHEN Ai-jing;YANG Yan-hua;State Power Investment Corporation Research Institute;National Energy Key Laboratory of Nuclear Power Software;Shanghai Jiao Tong University;

【机构】 国家电投集团科学技术研究院有限公司； 国家能源核电软件重点实验室； 上海交通大学核能科学与工程学院；

【摘要】 在设计基准事故下,反应堆冷却剂系统管道破裂和主蒸汽管道破裂引起的蒸汽释放会对安全壳造成热量、压力冲击,进而可能对安全壳的完整性造成破坏。本文针对AP1000的非能动安全壳冷却系统进行建模,考虑蒸汽在安全壳内壁面的冷凝和空气对安全壳外壁面的自然循环冷却作用,安全壳内的破口采用固定流量边界,外侧采用固定入口流量边界和出口压力边界,应用自主开发的COSINE程序进行计算,测试事故中安全壳内、外侧的压力、温度响应,并与对标程序GOTHIC计算得到的结果进行对比。通过对比两程序计算的压力、温度等参数,表明两程序的计算结果相符程度较好。更多还原

【Abstract】 Under design basic accident,steam blowing which is resulted from rupture of reactor cooling system pipes or rupture of main steam pipes will induce thermal and pressure impact on containment,then that will probably destroy containment integrity.Considering of steam condensation in containment and air natural circulation on the outer surface of containment,this analysis model describes passive containment cooling system(PCS) of AP1000.Applying constant mass flow boundary to the break in containment,at the same time,inlet mass flow and outlet pressure outside the containment are also constant.Pressure and temperature inside and outside the containment will be calculated by independently researched COSINE.Furthermore,above mentioned parameters which are calculated by COSINE and GOTHIC respectively will be compared.According to the comparison,the calculation results are corresponding acceptably.更多还原