Calculations for AP1000 nuclear power plant SGTR accident based on RELAP5/mod 3.3 program
AP1000 nuclear power plant model is founded via RELAP5/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 are 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 heat transfer tube leaking and make RCS be stable in a safe condition and to prevent SG overflowing and ADS actions occurring.
RCS cooldown and depressurization analysis of SGTR accident with SG safety valve stuck open
The Steam Generator Tube Rupture (SGTR) accident has been analyzed with RELAP5/MOD3 thermal hydraulic system analysis code under the conditions that the safety valve of affected SG is stuck open.The AFW is unavailable,and only one HPSI pump is available.It can be mitigated successfully if the operators take actions to cooldown and depressurize RCS within 150 min after the safety injection signal.The results show that the active core is covered by coolant before the break flow is terminated with the balance between primary and secondary side of affected SG at atmospheric pressure.
Trends in kiln drives
The heart of the cement plant is the rotary kiln, and continuous quality production of cement clinker depends on the continuous accurate performance of the rotary kiln drive.