Abstract
The post-commission LOCA (loss of coolant accident) analysis of the Qinshan NPP is introduced in this paper. The LB-LOCA (large break LOCA) an SB-LOCA (small break LOCA) of the Qinshan NPP were analysed by using the test source data from HPSI system and SI tank. For comparing with the FSAR (final safety analysis report), the initial conditions taking in computing simulation, calculation models and analysis code used in calculation were same as in FSAR. From the analysis, the safety of the Qinshan NPP is further confirmed in the LB-LOCA or SB-LOCA. It is also providing a revising base for the LB-LOCA and SB-LOCA analysis of FSAR. In addition, according to the ECCS (emergency core cooling system) design performance and operation mode of the Qinshan NPP, and referring to safety criteria of light water reactor LOCA, the evaluation of designing reliability and margin for the Qinshan NPP ECCS has been completed.
Zhujian, Zhang;
[1]
Shoulu, Xu
[2]
- Research Inst. of Nuclear Power Operation (China)
- Shanghai Nuclear Engineering Research and Development Inst., SH (China)
Citation Formats
Zhujian, Zhang, and Shoulu, Xu.
Post-commission LOCA analysis of Qinshan NPP.
China: N. p.,
1992.
Web.
Zhujian, Zhang, & Shoulu, Xu.
Post-commission LOCA analysis of Qinshan NPP.
China.
Zhujian, Zhang, and Shoulu, Xu.
1992.
"Post-commission LOCA analysis of Qinshan NPP."
China.
@misc{etde_10145263,
title = {Post-commission LOCA analysis of Qinshan NPP}
author = {Zhujian, Zhang, and Shoulu, Xu}
abstractNote = {The post-commission LOCA (loss of coolant accident) analysis of the Qinshan NPP is introduced in this paper. The LB-LOCA (large break LOCA) an SB-LOCA (small break LOCA) of the Qinshan NPP were analysed by using the test source data from HPSI system and SI tank. For comparing with the FSAR (final safety analysis report), the initial conditions taking in computing simulation, calculation models and analysis code used in calculation were same as in FSAR. From the analysis, the safety of the Qinshan NPP is further confirmed in the LB-LOCA or SB-LOCA. It is also providing a revising base for the LB-LOCA and SB-LOCA analysis of FSAR. In addition, according to the ECCS (emergency core cooling system) design performance and operation mode of the Qinshan NPP, and referring to safety criteria of light water reactor LOCA, the evaluation of designing reliability and margin for the Qinshan NPP ECCS has been completed.}
place = {China}
year = {1992}
month = {May}
}
title = {Post-commission LOCA analysis of Qinshan NPP}
author = {Zhujian, Zhang, and Shoulu, Xu}
abstractNote = {The post-commission LOCA (loss of coolant accident) analysis of the Qinshan NPP is introduced in this paper. The LB-LOCA (large break LOCA) an SB-LOCA (small break LOCA) of the Qinshan NPP were analysed by using the test source data from HPSI system and SI tank. For comparing with the FSAR (final safety analysis report), the initial conditions taking in computing simulation, calculation models and analysis code used in calculation were same as in FSAR. From the analysis, the safety of the Qinshan NPP is further confirmed in the LB-LOCA or SB-LOCA. It is also providing a revising base for the LB-LOCA and SB-LOCA analysis of FSAR. In addition, according to the ECCS (emergency core cooling system) design performance and operation mode of the Qinshan NPP, and referring to safety criteria of light water reactor LOCA, the evaluation of designing reliability and margin for the Qinshan NPP ECCS has been completed.}
place = {China}
year = {1992}
month = {May}
}