Abstract
The author deal with the descriptions of physical model of transient process in PWR plant and the function of ERP-IV (ERR-IV Transient Thermo-Hydraulic Analysis Code). The code has been developed for safety analysis and design transient. The code is characterized by the multi-loop long-term, short term, wide-range plant simulation with the capability to analyze natural circulation condition. The description of ERP-IV includes following parts: reactor, primary coolant loops, pressurizer, steam generators, main steam system, turbine, feedwater system, steam dump, relive valves, and safety valves in secondary side, etc.. The code can use for accident analysis, such as loss of all A.C. power to power plant auxiliaries (a station blackout), loss of normal feedwater, loss of load, loss of condenser vacuum and other events causing a turbine trip, complete loss of forced reactor coolant flow, uncontrolled rod cluster control assembly bank withdrawal. It can also be used for accident analysis of the emergency and limiting conditions, such as feedwater line break and main steam line rupture. It can also be utilized as a tool for system design studies, component design, setpoint studies and design transition studies, etc.
Anguo, Dai;
Jiahuan, Tang;
Huifu, Qian;
Zhikang, Gao
[1]
- Shanghai Nuclear Engineering Research and Design Inst. (China)
Citation Formats
Anguo, Dai, Jiahuan, Tang, Huifu, Qian, and Zhikang, Gao.
ERP-IV-A program for transient thermal-hydraulic analysis of PWR plant.
China: N. p.,
1987.
Web.
Anguo, Dai, Jiahuan, Tang, Huifu, Qian, & Zhikang, Gao.
ERP-IV-A program for transient thermal-hydraulic analysis of PWR plant.
China.
Anguo, Dai, Jiahuan, Tang, Huifu, Qian, and Zhikang, Gao.
1987.
"ERP-IV-A program for transient thermal-hydraulic analysis of PWR plant."
China.
@misc{etde_10152828,
title = {ERP-IV-A program for transient thermal-hydraulic analysis of PWR plant}
author = {Anguo, Dai, Jiahuan, Tang, Huifu, Qian, and Zhikang, Gao}
abstractNote = {The author deal with the descriptions of physical model of transient process in PWR plant and the function of ERP-IV (ERR-IV Transient Thermo-Hydraulic Analysis Code). The code has been developed for safety analysis and design transient. The code is characterized by the multi-loop long-term, short term, wide-range plant simulation with the capability to analyze natural circulation condition. The description of ERP-IV includes following parts: reactor, primary coolant loops, pressurizer, steam generators, main steam system, turbine, feedwater system, steam dump, relive valves, and safety valves in secondary side, etc.. The code can use for accident analysis, such as loss of all A.C. power to power plant auxiliaries (a station blackout), loss of normal feedwater, loss of load, loss of condenser vacuum and other events causing a turbine trip, complete loss of forced reactor coolant flow, uncontrolled rod cluster control assembly bank withdrawal. It can also be used for accident analysis of the emergency and limiting conditions, such as feedwater line break and main steam line rupture. It can also be utilized as a tool for system design studies, component design, setpoint studies and design transition studies, etc.}
place = {China}
year = {1987}
month = {Dec}
}
title = {ERP-IV-A program for transient thermal-hydraulic analysis of PWR plant}
author = {Anguo, Dai, Jiahuan, Tang, Huifu, Qian, and Zhikang, Gao}
abstractNote = {The author deal with the descriptions of physical model of transient process in PWR plant and the function of ERP-IV (ERR-IV Transient Thermo-Hydraulic Analysis Code). The code has been developed for safety analysis and design transient. The code is characterized by the multi-loop long-term, short term, wide-range plant simulation with the capability to analyze natural circulation condition. The description of ERP-IV includes following parts: reactor, primary coolant loops, pressurizer, steam generators, main steam system, turbine, feedwater system, steam dump, relive valves, and safety valves in secondary side, etc.. The code can use for accident analysis, such as loss of all A.C. power to power plant auxiliaries (a station blackout), loss of normal feedwater, loss of load, loss of condenser vacuum and other events causing a turbine trip, complete loss of forced reactor coolant flow, uncontrolled rod cluster control assembly bank withdrawal. It can also be used for accident analysis of the emergency and limiting conditions, such as feedwater line break and main steam line rupture. It can also be utilized as a tool for system design studies, component design, setpoint studies and design transition studies, etc.}
place = {China}
year = {1987}
month = {Dec}
}