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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

Abstract

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.

Keywords

Partial loss of feed BFP trip Natural circulation reactor RELAP5 

Abbreviations

BFP

Boiler feed pump

BWR

Boiling water reactor

CIES

Combined isolation and emergency safety

ECC

Emergency core cooling

GDWP

Gravity-driven water pool

IC

Isolation condenser

MHT

Main heat transport

MSIV

Main steam isolating valve

PIEs

Postulated initiating events

References

  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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