Mitigation schemes for avoiding very low pressure condition in the primary heat transport system during thermal shrinkage transients of 220 MWE PHWR nuclear power plant

摘要

In a Pressurised Heavy Water Reactor (PHWR) Nuclear Power Plant, those transients where large thermal shrinkage in the Primary Heat Transport (PHT) volume takes place, can result in the lowering of PHT system pressure. During Reactor trip, the minimum PHT pressure obtained can lead to unwanted actuation of Emergency Core Cooling System (ECCS). A reduction of the dip in the PHT system pressure can be achieved by increasing the net feed to the PHT volume i.e. by increasing the holdup inventory in a fixed boundary. Another option to maintain the PHT system pressure during such transients is to keep the PHT temperature at a higher value. This can be achieved by removing less heat from the primary coolant. To reduce the heat transfer from the primary coolant to the secondary coolant in the steam generator (SG), the SGPC (Steam Generator Pressure Controller) set point has to be increased during such incidences. This will lead to a higher steam pressure and temperature in the SG thus reducing the temperature difference and heat transfer between primary and secondary coolant. Analysis has been carried out using the integrated system process dynamics analysis code. This code incorporates the mathematical models for the primary and secondary heat transport systems, these models are based on coupled solutions of unsteady state mass, momentum and energy conservation equations. The present paper deals with the details of the different schemes considered along with the results arrived at.