Abstract
The natural circulation ability of PWR (pressurized water reactor) coolant system is one of inherent safeties of this kind NPP (nuclear power plant). According to the procedures and measured parameters of the natural circulation testing in Qinshan NPP, a LWR transient analysis code RETRAN-02 was used to simulate and calculate the ability of natural cooling circulation under different reactor power. For evaluating the reliability of experimental results and the impact of equipment parameters on the calculation, the comparison of pre-experiment analysis, post-experiment analysis and experimental results is completed.
Zhujiang, Zhang;
[1]
Shoulu, Xu
[2]
- Research Inst. of Nuclear Power Operation, Wuhan (China)
- Shanghai Nuclear Engineering Research and Development Inst., SH (China)
Citation Formats
Zhujiang, Zhang, and Shoulu, Xu.
Post-experiment analysis of natural circulation for Qinshan Nuclear Power Plant.
China: N. p.,
1992.
Web.
Zhujiang, Zhang, & Shoulu, Xu.
Post-experiment analysis of natural circulation for Qinshan Nuclear Power Plant.
China.
Zhujiang, Zhang, and Shoulu, Xu.
1992.
"Post-experiment analysis of natural circulation for Qinshan Nuclear Power Plant."
China.
@misc{etde_10109646,
title = {Post-experiment analysis of natural circulation for Qinshan Nuclear Power Plant}
author = {Zhujiang, Zhang, and Shoulu, Xu}
abstractNote = {The natural circulation ability of PWR (pressurized water reactor) coolant system is one of inherent safeties of this kind NPP (nuclear power plant). According to the procedures and measured parameters of the natural circulation testing in Qinshan NPP, a LWR transient analysis code RETRAN-02 was used to simulate and calculate the ability of natural cooling circulation under different reactor power. For evaluating the reliability of experimental results and the impact of equipment parameters on the calculation, the comparison of pre-experiment analysis, post-experiment analysis and experimental results is completed.}
place = {China}
year = {1992}
month = {Dec}
}
title = {Post-experiment analysis of natural circulation for Qinshan Nuclear Power Plant}
author = {Zhujiang, Zhang, and Shoulu, Xu}
abstractNote = {The natural circulation ability of PWR (pressurized water reactor) coolant system is one of inherent safeties of this kind NPP (nuclear power plant). According to the procedures and measured parameters of the natural circulation testing in Qinshan NPP, a LWR transient analysis code RETRAN-02 was used to simulate and calculate the ability of natural cooling circulation under different reactor power. For evaluating the reliability of experimental results and the impact of equipment parameters on the calculation, the comparison of pre-experiment analysis, post-experiment analysis and experimental results is completed.}
place = {China}
year = {1992}
month = {Dec}
}