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Technical Briefs

Assessment of the Code “PTCREEP ” for IPHWR Pressure Tube Ballooning Study

[+] Author and Article Information
P. Majumdar, B. Chatterjee, D. Mukhopadhyay, H. G. Lele

Reactor Safety Division, Bhabha Atomic Research Center, Mumbai 400 085, India

G. Nandan

 Indian Institute of Technology, Roorkee 247 667, India

J. Pressure Vessel Technol 133(1), 014503 (Jan 20, 2011) (4 pages) doi:10.1115/1.4001921 History: Received August 07, 2009; Revised April 23, 2010; Published January 20, 2011; Online January 20, 2011

In Indian pressurized heavy water reactor (PHWR), loss of coolant accident with simultaneous failure of emergency core cooling system can lead to significant temperature rise in the pressure tube (PT) with the system internal pressure varying from 9 MPa to 0.1 MPa during the event. This high temperature can cause metallurgical and geometrical changes in the PT. PT would deform plastically due to internal pressure and fuel weight. A computer code “PTCREEP ” based on physical models was developed to simulate the ballooning deformation expected during the channel heatup condition under internal pressure. This paper presents the assessment of the code PTCREEP against the set of experiments conducted with PT material used in Indian PHWRs.

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Copyright © 2011 by American Society of Mechanical Engineers
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References

Figures

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Figure 1

Schematic of IPHWR reactor channel

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Figure 2

Schematic for PT ballooning experiment

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Figure 3

Axial stations of thermocouples and potentiometers

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Figure 4

Prediction for an internal pressure of 2 MPa

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Figure 5

Prediction for an internal pressure of 4 MPa

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Figure 6

Prediction for an internal pressure of 6 MPa

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