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Please use this identifier to cite or link to this item: http://repository.iitr.ac.in/handle/123456789/11510
Title: Experimental investigation of sagging and ballooning for a completely voided pressure tube of Indian PHWR under heatup condition
Authors: Nandan G.
Sahoo, Pradeep K.
Kumar R.
Chatterjee B.
Mukhopadhyay D.
Lele H.G.
Published in: World Academy of Science, Engineering and Technology
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 the case of LOCA with/without failure of emergency core cooling system in a Pressurised Heavy Water Reactor (PHWR), the Pressure Tube (PT) temperature could rise significantly due to fuel heat up and gross mismatch of the 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 sagging (downward deformation) and ballooning (radial deformation) of PT for 220 MWe Indian PHWRs. Experiments are conducted both for sagging and ballooning of voided PTs. It is observed that sagging initiates at a temperature around 450C. The complete contact between PT and Calandria Tube (CT) occurs at around 585C. At 60 bar internal pressure and initial heat up rate of 2.37 oC/sec, ballooning of PT initiates at a temperature around 520C. The PT-CT contact is found to take place at 640 oC temperature and strain rates is found to be 0.125% per second. The structural integrity of PT is retained (no breach) for all the experiments. The PT heatup is found to be arrested after the contact between PT and CT, thus establishing moderator acting as an efficient heat sink for IPHWRs.
Citation: World Academy of Science, Engineering and Technology (2010), 61(): 197-204
URI: http://repository.iitr.ac.in/handle/123456789/11510
Issue Date: 2010
Keywords: Boiling heat transfer
Calandria tube
Pressure tube
Reactor safety
Thermo-mechanical deformation
ISSN: 2010376X
Author Scopus IDs: 57200563897
22835953900
55389796000
7201648525
7102685834
6602692797
Author Affiliations: Nandan, G., Mechanical and Industrial Engineering Department, Indian Institute of Technology, Roorkee, India
Sahoo, P.K., Mechanical and Industrial Engineering Department, Indian Institute of Technology, Roorkee, India
Kumar, R., Mechanical and Industrial Engineering Department, Indian Institute of Technology, Roorkee, India
Chatterjee, B., Reactor Safety Division, Bhabha Atomic Research Centre, India
Mukhopadhyay, D., Reactor Safety Division, Bhabha Atomic Research Centre, India
Lele, H.G., Reactor Safety Division, Bhabha Atomic Research Centre, India
Corresponding Author: Nandan, G.; Mechanical and Industrial Engineering Department, Indian Institute of Technology, Roorkee, India; email: gopalnandan@gmail.com
Appears in Collections:Journal Publications [ME]

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