Calculations for AP1000 nuclear power plant SGTR accident based on RELAP5/mod 3.3 program

摘要

AP1000 nuclear power plant model is founded via RHLAP5/mod 3.3 program in detail. Refer to SGTR accident basic assumptions in the safety analysis report, calculations for AP1000 nuclear power plant SGTR accident are carried out. And through comparison between the result got and the result from safety analysis report calculated by LOFTTR2 program, the two results arc very consistent. It's found that even if the operators do not interfere, AP1000 nuclear power plant protection systems and passive design measures will trigger an automatic response measures, it can terminate the SG heal transfer tube leaking and make RCS be stable in a safe condition and to prevent SG overflowing and ADS actions occurring.