Thermo-mechanical behavior of Pressure Tube of Indian PHWR at 20 bar

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

Research output: Contribution to journalArticle

1 Citation (Scopus)

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, 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 ballooning (radial deformation) of PT for 220 MWe IPHWRs. Experiments have been conducted by covering the CT by ceramic fibers and then by submerging CT in water of voided PTs. In both the experiments, it is observed that ballooning initiates at a temperature around 665C and complete contact between PT and Caldaria Tube (CT) occurs at around 700C approximately. The strain rate is found to be 0.116% 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.
Original languageEnglish
Pages (from-to)205-213
Number of pages9
JournalWorld Academy of Science, Engineering and Technology
Volume61
Publication statusPublished - 2010

Fingerprint

Loss of coolant accidents
Heavy water reactors
Ceramic fibers
Moderators
Piping systems
Experiments
Heat generation
Heat sinks
Structural integrity
Cooling systems
Strain rate
Pipe
Temperature
Hot Temperature
Water

Cite this

Nandan, G., Sahoo, P. K., Kumar, R., Chatterjee, B., Mukhopadhyay, D., & Lele, H. G. (2010). Thermo-mechanical behavior of Pressure Tube of Indian PHWR at 20 bar. World Academy of Science, Engineering and Technology, 61, 205-213.
Nandan, G. ; Sahoo, P.K. ; Kumar, R. ; Chatterjee, B. ; Mukhopadhyay, D. ; Lele, H.G. / Thermo-mechanical behavior of Pressure Tube of Indian PHWR at 20 bar. In: World Academy of Science, Engineering and Technology. 2010 ; Vol. 61. pp. 205-213.
@article{7e5bd9cc9f484654973d93c459f3ad25,
title = "Thermo-mechanical behavior of Pressure Tube of Indian PHWR at 20 bar",
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, 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 ballooning (radial deformation) of PT for 220 MWe IPHWRs. Experiments have been conducted by covering the CT by ceramic fibers and then by submerging CT in water of voided PTs. In both the experiments, it is observed that ballooning initiates at a temperature around 665C and complete contact between PT and Caldaria Tube (CT) occurs at around 700C approximately. The strain rate is found to be 0.116{\%} 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.",
author = "G. Nandan and P.K. Sahoo and R. Kumar and B. Chatterjee and D. Mukhopadhyay and H.G. Lele",
note = "Cited By :1 Export Date: 19 June 2018",
year = "2010",
language = "English",
volume = "61",
pages = "205--213",
journal = "World Academy of Science, Engineering and Technology",
issn = "2010-376X",
publisher = "World Academy of Science Engineering and Technology",

}

Nandan, G, Sahoo, PK, Kumar, R, Chatterjee, B, Mukhopadhyay, D & Lele, HG 2010, 'Thermo-mechanical behavior of Pressure Tube of Indian PHWR at 20 bar', World Academy of Science, Engineering and Technology, vol. 61, pp. 205-213.

Thermo-mechanical behavior of Pressure Tube of Indian PHWR at 20 bar. / Nandan, G.; Sahoo, P.K.; Kumar, R.; Chatterjee, B.; Mukhopadhyay, D.; Lele, H.G.

In: World Academy of Science, Engineering and Technology, Vol. 61, 2010, p. 205-213.

Research output: Contribution to journalArticle

TY - JOUR

T1 - Thermo-mechanical behavior of Pressure Tube of Indian PHWR at 20 bar

AU - Nandan, G.

AU - Sahoo, P.K.

AU - Kumar, R.

AU - Chatterjee, B.

AU - Mukhopadhyay, D.

AU - Lele, H.G.

N1 - Cited By :1 Export Date: 19 June 2018

PY - 2010

Y1 - 2010

N2 - 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, 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 ballooning (radial deformation) of PT for 220 MWe IPHWRs. Experiments have been conducted by covering the CT by ceramic fibers and then by submerging CT in water of voided PTs. In both the experiments, it is observed that ballooning initiates at a temperature around 665C and complete contact between PT and Caldaria Tube (CT) occurs at around 700C approximately. The strain rate is found to be 0.116% 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.

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 the case of LOCA with/without failure of emergency core cooling system in a Pressurised Heavy water Reactor, 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 ballooning (radial deformation) of PT for 220 MWe IPHWRs. Experiments have been conducted by covering the CT by ceramic fibers and then by submerging CT in water of voided PTs. In both the experiments, it is observed that ballooning initiates at a temperature around 665C and complete contact between PT and Caldaria Tube (CT) occurs at around 700C approximately. The strain rate is found to be 0.116% 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.

M3 - Article

VL - 61

SP - 205

EP - 213

JO - World Academy of Science, Engineering and Technology

JF - World Academy of Science, Engineering and Technology

SN - 2010-376X

ER -