Reliability studies of decay heat removal system

Passive systems have been implemented in most of the advanced reactors in order to improve the availability of the plant. In this paper the methodology used for performing the passive system reliability analysis has been discussed. A case study on passive decay heat removal system of large sized PHWRs has also been discussed. Based on the thermal hydraulic analysis failure points have been generated and the failure surface has been developed. Finally by using the Monte Carlo simulation technique failure probability has been estimated.

[1]  Francesco Saverio D'Auria,et al.  Transient and stability analysis in single-phase natural circulation , 2004 .

[2]  Hiroyasu Mochizuki,et al.  Core coolability of an ATR by heavy water moderator in situations beyond design basis accidents , 1993 .

[3]  Algirdas Kaliatka,et al.  Approach to accident management in RBMK-1500 , 2008 .

[4]  Pallippattu Krishnan Vijayan,et al.  Effect of Coolant Inventories and Parallel Loop Interconnections on the Natural Circulation in Various Heat Transport Systems of a Nuclear Power Plant during Station Blackout , 2008 .

[5]  Pallippattu Krishnan Vijayan,et al.  Analysis of metastable regimes in a parallel channel single phase natural circulation system with RELAP5/MOD3.2 , 2007 .

[6]  Rajesh Kumar,et al.  Selection of a steam generator pressure control program for a 500 MWe pressurized heavy water reactor power plant through transient analysis , 2003 .

[7]  Francesco Saverio D'Auria,et al.  Thermal-hydraulic performance of primary system of RBMK in case of accidents , 2008 .

[8]  Rajesh Kumar,et al.  Transient analysis following tripping of a primary circulating pump for 500-MWe PHWR power plant , 2003 .

[9]  Rajesh Kumar,et al.  Logic modification to avoid ECCS lineup in the primary heat transport system during thermal shrinkage transients of 220 MWe PHWR nuclear power plant , 2003 .

[10]  Francesco Saverio D'Auria,et al.  Analysis of single-phase natural circulation experiments by system codes , 1999 .

[11]  Tatsuya Kondo,et al.  Development of the advanced thermal reactor in Japan , 1993 .

[12]  Chien-Hsiung Lee,et al.  IIST and LSTF counterpart test on PWR station blackout transient , 1997 .