Research on Reactor Safety Analysis Method due to Thermal System Change of Secondary Circuit

doi: 10.13832/j.jnpe.2017.01.0046

• Zhang Zhao^1,2 , 
• Tang Qi³ , 
• WEi Yanhui³ , 
• SHen Rongfa¹ , 
• SHeng Guolong¹ , 
• Yan Junjie² , 
• Zhong Daotong²

• 1. Suzhou Nuclear Power Research Institute, Shenzhen, Guangdong, 518000, China;

• 2. State Key Laboratory of Multiphase Flow in Power Engineering, Xi'an Jiaotong University, Xi'an, 710049, China;

• 3. Daya Bay Nuclear Power Operations and Management Co. Ltd., Shenzhen, Guangdong, 518000, China