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Probabilistic Safety Assessment Studies

In addition to the deterministic analysis, Probabilistic safety assessment (PSA) is being used as part of the decision making process to assess the level of safety in Indian nuclear power plants. To support AERB activities in this area, PSA and reliability has been identified as one of the research activities at SRI. Some of the important activities in PSA include regulatory review of PSA documents, passive system reliability analysis, software reliability, external events PSA studies, multi-unit risk assessment, etc..

Risk Assessment Studies

Accomplishment of Seismic Re-evaluation of FBTR

Seismic evaluation of a nuclear installation is an important activity. With the changing seismic design and safety requirements, it is also important to re-evaluate existing nuclear plants. In this context, a seismic re-evaluation exercise of a fast breeder test reactor (FBTR) at Kalpakkam is carried out. The safety objectives identified for re-evaluation are

  • Safe shutdown of the plant
  • maintaining in safe shutdown condition,
  • long term decay heat removal, and
  • containment of radioactivity.
External Flooding Probabilistic Safety Analysis of PFBR
Hybrid approach for estimation of Software Reliability in Nuclear Safety Systems
Common Cause Failure Analysis for Engineered Safety Systems Using Alpha Factors Obtained by Mapping Technique
Analysis of Damper Control Systems and its Impact on SGDHRS Reliability
Risk Assessment of Multi-Unit Nuclear Power Plant Sites against External Hazards

विजिटर काउण्ट: 4318740

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परमाणु ऊर्जा नियामक परिषद, नियामक भवन अणुशक्तिनगर,, मुंबई 400094, भारत,

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