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Please use this identifier to cite or link to this item: http://repository.iitr.ac.in/handle/123456789/12396
Title: Study of ballooning of a completely voided pressure tube of Indian PHWR under heat up condition
Authors: Nandan G.
Majumdar P.
Sahoo, Pradeep K.
Kumar R.
Chatterjee B.
Mukhopadhyay D.
Lele H.G.
Published in: Nuclear Engineering and Design
Abstract: In a nuclear reactor, loss of coolant accident (LOCA) considers wide range of postulated damage or rupture of pipe in the heat transport piping system. In case of LOCA with/without failure of emergency core cooling system in a Pressurized Heavy Water Reactor, the pressure tube (PT) temperature can rise significantly due to fuel heat up and gross mismatch of heat generation and heat removal in the affected channel. The extent and nature of deformation is important from reactor safety point of view. Experimental set-ups have been designed and fabricated to simulate ballooning (radial deformation) of PT for 220 MWe IPHWRs. Experiments have been conducted using voided PTs at 4 and 6 MPa internal pressure at different heating rates. It is observed that at 4 MPa and 6 MPa internal pressure, the PT sagged at about 500 °C before the ballooning initiation. The ballooning initiates at a temperature around 625 °C and contact between PT and Calandria Tube (CT) occurs at around 680 °C, respectively, for 4 MPa and the same was at 550 °C and 640 °C for 6 MPa. The structural integrity of PT is retained (no breach) for all the experiments. The PT heat up is found to be arrested after the contact between PT and CT, thus establishing the moderator acting as an efficient heat sink for IPHWRs. A thermal creep model 'PTCREEP' has been developed to predict creep behaviour of the PT of IPHWR. It is found that the contact time predicted by PTCREEP is very close to the experimental result. Hence, PTCREEP can be used for the prediction of the ballooning behaviour of the PT for IPHWR in case of LOCA for the operating temperature and pressure range. © 2011 Elsevier B.V. All rights reserved.
Citation: Nuclear Engineering and Design (2012), 243(): 301-310
URI: https://doi.org/10.1016/j.nucengdes.2011.11.007
http://repository.iitr.ac.in/handle/123456789/12396
Issue Date: 2012
ISSN: 295493
Author Scopus IDs: 57200563897
35613969100
22835953900
55389796000
7201648525
7102685834
6602692797
Author Affiliations: Nandan, G., Department of Mechanical and Industrial Engineering, Indian Institute of Technology, Roorkee, India
Majumdar, P., Reactor Safety Division, Bhabha Atomic Research Centre, Trombay, Mumbai, India
Sahoo, P.K., Department of Mechanical and Industrial Engineering, Indian Institute of Technology, Roorkee, India
Kumar, R., Department of Mechanical and Industrial Engineering, Indian Institute of Technology, Roorkee, India
Chatterjee, B., Reactor Safety Division, Bhabha Atomic Research Centre, Trombay, Mumbai, India
Mukhopadhyay, D., Reactor Safety Division, Bhabha Atomic Research Centre, Trombay, Mumbai, India
Lele, H.G., Reactor Safety Division, Bhabha Atomic Research Centre, Trombay, Mumbai, India
Corresponding Author: Sahoo, P.K.; Department of Mechanical and Industrial Engineering, Indian Institute of Technology, Roorkee, India; email: sahoofme@iitr.ernet.in
Appears in Collections:Journal Publications [ME]

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