REFERENCES
- S. K. LOYALKA, Prog. Nucl. Energy, 12, 1 (1983).
- “Document & Users’ Manual on Post-Accident Containment System Response,” NPC/DM/01550/1/R2/2008, Nuclear Power Corporation of India Limited (Aug. 2008).
- J. J. CARBAJO, “Heat Transfer Coefficients Under LOCA Conditions in Containment Building,” Nucl. Eng. Des., 65, 369 (1981).
- J. GREEN and K. ALMENAS, “An Overview of the Primary Parameters and Methods for Determining Condensation Heat Transfer to Containment Structures,” Nucl. Safety, 37, 1, 26 (1996).
- M. KANSAL, N. MOHAN, and S. S. BAJAJ, “Heat Transfer Coefficient for Condensing Steam on Containment Structures,” 16th National Heat and Mass Transfer Conf., Calcutta, 2002.
- S. S. BAJAJ, M. KANSAL, and N. MOHAN, “Validation of Containment Computer Code PACSR Against Vapor Suppression Pool Experiments,” MAPP/01500/89/B/3242 (1989).
- S. BAJAJ and M. KANSAL, “Verification of Computer Code PACSR Against ISP-23 on HDR Containment Model,” Kaiga/21200/94/B/216 (Jan. 13, 1994).
- S. S. BAJAJ, N. MOHAN, and M. KANSAL, “Verification of Computer Code PACSR Against Experiment D15 on Battelle Frankfurt Containment Model,” NPC/01540/96/B/8131 (1996).
- “TAPS-3&4 Safety Report,” Vol. II, Nuclear Power Corporation of India Limited (June 2004).
- R. N. BHAWAL et al., “Fission Products Release Source Term Following a LOCA in Water Reactors: A State of the Art Review,” Kalpakkam (1983).