Analysis of the Thermal Hydraulic Consequences Following Common Mode Pump Seizure in a Nuclear Power Plant

[+] Author and Article Information
B. Chatterjee, S. K. Gupta, H. S. Kushwaha, 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), 415-417 (Nov 08, 2002) (3 pages) doi:10.1115/1.1465437 History: Received December 04, 2000; Revised December 18, 2001; Online November 08, 2002
Copyright © 2002 by ASME
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Kao,  L., and Huang,  P.-H., 1999, “Pressurised Water Reactor Coolant Pump Locked Rotor Analysis Methodology using RETRAN-02 and FREY,” Nucl. Technol., 127, pp 382–388.
Fischer, S. R., 1978, “RELAP4/MOD6: A Computer Program for Transient Thermal Hydraulic Analysis of Nuclear Reactors and Related Systems, User’s Manual,” S. Idaho National Engineering Laboratory report no. CDAP-TR0003.


Grahic Jump Location
Schemetic diagram of PHT system
Grahic Jump Location
Upstream suction pressure
Grahic Jump Location
Reactor outlet header pressure



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