1. Anderson, L.E., 1983. Effects of a hypothetical core melt accident on a PWR vessel with top-entry instrument. EPRI IDCOR Program Technical Report 15.2A.
2. Chambers, R.S., 1987. A finite element analysis of a pressurized containment vessel during core melt down, SAND 87-2183.
3. Finite element analyses of a BWR vessel and penetration under severe accident conditions;Chavez;Nucl. Eng. Des.,1994
4. Chu, T.Y., Pilch, M.M., Bentz, J.H., 1997. An assessment of the effects of heat flux distribution and penetration on the creep rupture of a reactor vessel lower head. Twelfth Proceedings of Nuclear Thermal Hydraulics, 1997 ANS Winter Meeting. Albuquerque, NM, pp. 135–144.
5. Degaltsev, Y., Karlov, O., Vasiliev, B., Ostapov, E., 1997. Investigation of high-temperature strength of 15X2HMFA vessel steel in temperature range of 1000–1300°C, Rep. RP-TR-29. Russian Research Center “Kurchatov Institute”, OECD RASPLAV Project.