Transient Following Partial Loss of Feed Water for Thorium-based Natural Circulation Reactor

  • A. D. ContractorEmail author
  • A. Srivastava
  • Rajesh Kumar
  • B. Chatterjee
Conference paper


A new reactor system under design study is a vertical pressure tube-type boiling light water cooled and heavy water moderated. Main heat transport system consists of reactor core, core inlet and outlet extensions, inlet feeders, tailpipes, steam drums, downcomer, and inlet header. It incorporates several advanced passive safety features, e.g., heat removal through natural circulation both during normal operation and reactor shutdown without the use of any coolant pump. Safety remains the paramount consideration in the design, while plant availability is the next. Several reactor trip set points are provided in design to tackle the disturbances in operation, and many safety systems are provided to mitigate different accidental conditions. A major objective of the reactor design is to provide a capability to withstand a wide range of postulated events (PIEs) without exceeding the acceptance limits, thereby maintaining fuel integrity. Partial loss of feed water is one of such PIEs. Following article highlights the modeling and overall transient behavior and its safety implication.


Partial loss of feed BFP trip Natural circulation reactor RELAP5 



Boiler feed pump


Boiling water reactor


Combined isolation and emergency safety


Emergency core cooling


Gravity-driven water pool


Isolation condenser


Main heat transport


Main steam isolating valve


Postulated initiating events


  1. 1.
    R.K. Sinha, A. Kakodkar, Design and development of the AHWR-the Indian Thorium fuelled innovative nuclear reactor. Nucl. Eng. Des. 236, 683–700 (2006)CrossRefGoogle Scholar
  2. 2.
    G.D. Fletcher, R.R. Schultz, RELAP5/MOD3.2 Code Manual (Idaho National Engineering Laboratory, Idaho, 1995)Google Scholar

Copyright information

© Springer Nature Singapore Pte Ltd. 2019

Authors and Affiliations

  • A. D. Contractor
    • 1
    Email author
  • A. Srivastava
    • 1
  • Rajesh Kumar
    • 1
  • B. Chatterjee
    • 1
  1. 1.Reactor Safety DivisionBhabha Atomic Research CentreTrombayIndia

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