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Estimation of Large Early Release Frequency for Advanced Heavy Water Reactor

  • T. V. SanthoshEmail author
  • I. Thangamani
  • A. Srivastava
  • Gopika Vinod
  • Vishnu Verma
  • P. K. Vijayan
Conference paper

Abstract

A framework for estimation of large early release frequency of a nuclear power plant is presented in this paper. The study aims at evaluating the reliability of containment safety features and analysing the physical processes such as timing and magnitude of radioactivity release. The release categories were formulated based on the amount of release of fission products (FPs) and their time of release. Reliability analysis of engineered safety features (ESFs) of containment was carried out using fault tree technique. The end states of containment event trees were formulated qualitatively based on the expert judgement, and the release categories were assigned accordingly. For interfacing with Level 1 probabilistic safety assessment (PSA), the plant damage categories were modified to include aspects such as time and extent of core damage and amount of metal–water reaction. Containment event trees were developed for these plant damage states, and the large early release frequency (LERF) was estimated for the advanced heavy water reactor (AHWR).

Keywords

Probabilistic safety assessment Large early release frequency Loss of coolant accident Emergency preparedness Nuclear power plant 

References

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Copyright information

© Springer Nature Singapore Pte Ltd. 2019

Authors and Affiliations

  • T. V. Santhosh
    • 1
    Email author
  • I. Thangamani
    • 1
  • A. Srivastava
    • 1
  • Gopika Vinod
    • 1
  • Vishnu Verma
    • 1
  • P. K. Vijayan
    • 1
  1. 1.Reactor Safety DivisionBhabha Atomic Research Centre, TrombayMumbaiIndia

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