A Loss-of-RHR Event under the Various Plant Configurations in Low Power or Shutdown Conditions

  • Seul, Kwang-Won (Korea Institute of Nuclear Safety, Advanced Reactor Department) ;
  • Bang, Young-Seok (Korea Institute of Nuclear Safety, Advanced Reactor Department) ;
  • Lee, Sukho (Korea Institute of Nuclear Safety, Advanced Reactor Department) ;
  • Kim, Hho-Jung (Korea Institute of Nuclear Safety, Advanced Reactor Department)
  • Published : 1997.05.01

Abstract

A present study addresses a loss-of-RHR event as an initiating event under specific low power or shutdown conditions. Two typical plant configurations, cold leg opening case with water-filled steam generators and pressurizer opening case with emptied steam generators, were evaluated using the RELAP5/ MOD3.2 code. The calculation was compared with the experiment conducted at ROSA-IV/LSTF in Japan. As a result, the code was capable of simulating the system transient behavior following the event. Especially, thermal hydraulic transport processes including non-condensable gas behavior were reasonably predicted with an appropriate time step and CPU time. However, there were some code deficiencies such as too large system mass errors and severe flow oscillations in core region.

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