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TECHNICAL PAPERS

Analysis of Possibility of Pressure Tube Cold Pressurization During ECCS Injection for a Small Break LOCA

[+] Author and Article Information
D. Mukhopadhyay, S. K. Gupta, V. Venkat Raj

Health, Safety and Environment Group, Bhabha Atomic Research Centre, Reactor Safety Division, BARC, Mumbai 400 085, India

J. Pressure Vessel Technol 124(4), 483-486 (Nov 08, 2002) (4 pages) doi:10.1115/1.1465438 History: Received December 04, 2000; Revised December 18, 2001; Online November 08, 2002
Copyright © 2002 by ASME
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References

Fischer, S. R., 1978, “RELAP4/MOD6: A Computer Program for Transient Thermal-Hydraulic Analysis of Nuclear Reactors and Related Systems, User’s Manual,” Technical Report No. CDAP TR003, Idaho National Engineering Laboratory (INEL), ID.
Wallace, C., Andrew, Shek, K., Gordon, Lepik, K., Olev, “Effects of Hydride Morphology on Zr-2.5 Nb Fracture Toughness,” Proc. 8th International Symposium on Zirconium in the Nuclear Industry, eds, Leo F. P. Vanswam et al., ASTM STP 1023, pp. 66–87.

Figures

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Schematic of primary heat transport (PHT) system
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Nodalization scheme used for PHT system simulation
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Characteristic for an irradiated hydrided PT of zircaloy-2 showing maximum permissible pressure to avoid fracture
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Pressure tube pressure transient for small break at RIH
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Pressure tube fluid temperature transient for small break at RIH
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Pressure tube pressure transient for small break at ROH
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Pressure tube fluid temperature transient for small break at ROH
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Comparison of computed PT pressure during LOCA and PT characteristic for different PT temperature

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