Nonlinear Dynamic Analysis of RCS LOCA Based on Secondary Development of ANSYS
Research of loss of coolant accident (LOCA) postulated on the nuclear reactor coolant system (RCS) was investigated with ANSYS program. Secondary development of ANSYS was performed to form the customized module for implementing effective and efficient RCS LOCA nonlinear analysis. A standard analysis procedure was established. It has following functions, such as parameters and modular system modeling, automatically set break, static pilot analysis, LOCA nonlinear dynamic calculation and automatic reports generation. Main pipes, Steam generator and reactor coolant pump models were molded by parameterized modular modeling method. Those models considered the nonlinear factors, such as material nonlinearities, gap and so on, constructed component model libraries of RCS. Comparing the results calculated by ANSYS and program-specific, it is showed that the results are generally consistent.
Nuclear Reactor Coolant System LOCA Nonlinear Dynamic Analysis Secondary Development of ANSYS
Qi Huan-huan Zeng zhong-xiu
National key laboratory of reactor system design technology, Nuclear power institute of china,Chengdu 610041 China
国际会议
上海
英文
334-338
2011-10-21（万方平台首次上网日期，不代表论文的发表时间）