Study of ballooning of a completely voided pressure tube of Indian PHWR under heat up condition

G. Nandan, P. Majumdar, P.K. Sahoo, R. Kumar, B. Chatterjee, D. Mukhopadhyay, H.G. Lele

Research output: Contribution to journalArticle

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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.
Original languageEnglish
Pages (from-to)301-310
Number of pages10
JournalNuclear Engineering and Design
Volume243
DOIs
Publication statusPublished - 2012

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tubes
heat
loss of coolant
Loss of coolant accidents
accidents
accident
internal pressure
creep
Hot Temperature
heavy water reactors
Creep
reactor safety
Heavy water reactors
moderators
heat generation
nuclear reactors
cooling systems
emergencies
heat sinks
Moderators

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Nandan, G. ; Majumdar, P. ; Sahoo, P.K. ; Kumar, R. ; Chatterjee, B. ; Mukhopadhyay, D. ; Lele, H.G. / Study of ballooning of a completely voided pressure tube of Indian PHWR under heat up condition. In: Nuclear Engineering and Design. 2012 ; Vol. 243. pp. 301-310.
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Study of ballooning of a completely voided pressure tube of Indian PHWR under heat up condition. / Nandan, G.; Majumdar, P.; Sahoo, P.K.; Kumar, R.; Chatterjee, B.; Mukhopadhyay, D.; Lele, H.G.

In: Nuclear Engineering and Design, Vol. 243, 2012, p. 301-310.

Research output: Contribution to journalArticle

TY - JOUR

T1 - Study of ballooning of a completely voided pressure tube of Indian PHWR under heat up condition

AU - Nandan, G.

AU - Majumdar, P.

AU - Sahoo, P.K.

AU - Kumar, R.

AU - Chatterjee, B.

AU - Mukhopadhyay, D.

AU - Lele, H.G.

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AB - 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.

U2 - 10.1016/j.nucengdes.2011.11.007

DO - 10.1016/j.nucengdes.2011.11.007

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EP - 310

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JF - Nuclear Engineering and Design

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