1. 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.
2. Gupta, S. K., Venkat Raj, V., and Kakodkar, A., 1996, “A Study of Indian PHWR Reactor Channel Under Prolonged Deteriorated Flow Conditions,” Proc., IAEA TCM on Advances in Heavy Water Reactors, Bombay, India.
3. Shewfelt, R. S. W., Lyall, L. W., and Godin, D. P., 1984, “A High Temperature Creep Model for Zr-2.5 wt percent Nb Pressure Tubes,” J. Nucl. Mater., 125, pp. 228–235.