유체기계공업학회:학술대회논문집

Korean Society for Fluid machinery (한국유체기계학회)
권호 표지

A Study on Hydraulic Transients of Letdown System of Nuclear Power Plant

원자력발전소 유출계통의 과도현상에 대한 연구

  • 김민 (한국전력기술(주) 원자로설계개발단) ;
  • 정장규 (한국전력기술(주) 원자로설계개발단) ;
  • 김은기 (한국전력기술(주) 원자로설계개발단) ;
  • 노태선 (한국전력기술(주) 원자로설계개발단) ;
  • 이성노 (충남대학교) ;
  • 유성연 (충남대학교)
  • Published : 2002.12.01
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Abstract

The letdown system of pressurized water reactor (PWR) nuclear fewer plants had experienced instabilities in letdown system due to unacceptable flow characteristics of control valves. The Korean Standard Nuclear Power Plants (KSNPs) have three flow paths in parallel for letdown new control. Each flow path consists of two offices and one isolation valve. This study evaluates the effect of orifice arrangement and valve stroke time of letdown isolation valve on the system transients because sudden flow changes due to valve actuation can generate high pressure peaks in letdown line. A pressure transient analysis has been preformed to evaluate the impact of dynamic transients. This analysis uses MMS which is a simulation code developed by EPRI based on the method of characteristics. The result shows that the pressure peak is reduced in the continuous arrangement but negligible. Additionally, it shows that the stroke time of linear type flog valve greater than 15 seconds can give more stable performance.

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