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Please use this identifier to cite or link to this item: http://repository.iitr.ac.in/handle/123456789/11516
Title: Experimental investigation on circumferential and axial temperature gradient over fuel channel under LOCA
Authors: Yadav A.K.
Kumar R.
Gupta, Akhilesh Kumar
Chatterjee B.
Mukhopadhyay D.
Lele H.G.
Published in: Heat and Mass Transfer/Waerme- und Stoffuebertragung
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. © 2013 Springer-Verlag Berlin Heidelberg.
Citation: Heat and Mass Transfer/Waerme- und Stoffuebertragung (2014), 50(6): 737-746
URI: https://doi.org/10.1007/s00231-013-1279-8
http://repository.iitr.ac.in/handle/123456789/11516
Issue Date: 2014
Publisher: Springer Verlag
ISSN: 9477411
Author Scopus IDs: 55520507000
55389796000
55491955100
7201648525
7102685834
6602692797
Author Affiliations: Yadav, A.K., Indian Institute of Technology Roorkee, Roorkee, India
Kumar, R., Indian Institute of Technology Roorkee, Roorkee, India
Gupta, A., Indian Institute of Technology Roorkee, Roorkee, India
Chatterjee, B., Reactor Safety Division, Bhabha Atomic Research Centre, Mumbai, India
Mukhopadhyay, D., Reactor Safety Division, Bhabha Atomic Research Centre, Mumbai, India
Lele, H.G., Reactor Safety Division, Bhabha Atomic Research Centre, Mumbai, India
Corresponding Author: Yadav, A.K.; Indian Institute of Technology Roorkee, Roorkee, India; email: ashwinikumaryadav@gmail.com
Appears in Collections:Journal Publications [ME]

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