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Heat and Mass Transfer

, Volume 50, Issue 6, pp 737–746 | Cite as

Experimental investigation on circumferential and axial temperature gradient over fuel channel under LOCA

  • Ashwini Kumar YadavEmail author
  • Ravi kumar
  • Akhilesh Gupta
  • Barun Chatterjee
  • Deb Mukhopadhyay
  • H. G. Lele
Original

Abstract

In a nuclear reactor temperature rises drastically in fuel channels under loss of coolant accident due to failure of primary heat transportation system. Present investigation has been carried out to capture circumferential and axial temperature gradients during fully and partially voiding conditions in a fuel channel using 19 pin fuel element simulator. A series of experiments were carried out by supplying power to outer, middle and center rods of 19 pin fuel simulator in ratio of 1.4:1.1:1. The temperature at upper periphery of pressure tube (PT) was slightly higher than at bottom due to increase in local equivalent thermal conductivity from top to bottom of PT. To simulate fully voided conditions PT was pressurized at 2.0 MPa pressure with 17.5 kW power injection. Ballooning initiated from center and then propagates towards the ends and hence axial temperature difference has been observed along the length of PT. For asymmetric heating, upper eight rods of fuel simulator were activated and temperature difference up-to 250 °C has been observed from top to bottom periphery of PT. Such situation creates steep circumferential temperature gradient over PT and could lead to breaching of PT under high pressure.

Keywords

Heat Transfer Rate Pressure Tube Anticlockwise Direction Axial Temperature Gradient Fuel Channel 
These keywords were added by machine and not by the authors. This process is experimental and the keywords may be updated as the learning algorithm improves.

Abbreviations

CANDU

Canadian Deuterium Uranium

LOCA

Loss of coolant accident

ECCS

Emergency core cooling system

IPHWR

Indian pressurized heavy water reactor

PT

Pressure tube

CT

Calandria tube

Notes

Acknowledgments

The authors are thankful to Bhabha Atomic Research Centre (BARC), Mumbai, India for providing financial support to this project.

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Copyright information

© Springer-Verlag Berlin Heidelberg 2013

Authors and Affiliations

  • Ashwini Kumar Yadav
    • 1
    Email author
  • Ravi kumar
    • 1
  • Akhilesh Gupta
    • 1
  • Barun Chatterjee
    • 2
  • Deb Mukhopadhyay
    • 2
  • H. G. Lele
    • 2
  1. 1.Indian Institute of Technology RoorkeeRoorkeeIndia
  2. 2.Reactor Safety DivisionBhabha Atomic Research CentreMumbaiIndia

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