Study on the Performance Behavior of Passive Containment Cooling System in a Natural Circulation BWR during a Postulated Accident Condition
Passive systems are playing prominent role in the development of innovative nuclear reactor system due to their simplicity, enhanced safety, reliability and economy. These systems are being considered for normal operation as well as safety of reactor following a postulated accident scenario to eliminate the scenarios arising out of failure of active systems as well as to minimize the operator intervention. Indian innovative reactor AHWR being designed for thorium utilization employs various passive safety concepts. As containment is the ultimate barrier to the release of radioactivity, passive concepts are being employed in BWR’s for the removal of the steam load in the containment during a postulated accident condition like LOCA. The concept of passive containment cooling system comprise of inclined tube heat exchangers lying underneath an elevated pool that removes the heat from the steam-air atmosphere of containment following a LOCA by natural circulation of water inside the tubes. The steam condenses on the external surface of tubes of PCCS in addition to the wall of the containment which in turn depressurizes the containment. This paper deals with the performance assessment of PCCS of Natural Circulation BWR during a postulated design basis LOCA by using a best estimate code RELAP5/Mod3.2.
Passive Containment Cooling Natural Circulation Passive Systems LOCA
Mukesh Kumar Vikas Jain A.K. Nayak P. K. Vijayan D. Saha R.K. Sinha
Reactor Engineering Division, Reactor Design & Development Group Bhabha Atomic Research Centre, Trombay, Mumbai 400085, India
国际会议
上海
英文
1802-1810
2010-10-10（万方平台首次上网日期，不代表论文的发表时间）