References
- RETRAN-3D A Program For Transient Thermal Hydraulic Analysis of Complex Fluid Flow System, NP-7450 EPRI
- Regulatory Guide 1.154 Format and Content of Plant-Specific Pressurized Thermal Shock Safety Analysis Reports for Pressurized Water Reactors USNRC
- Heat Conduction Oezisik, M.N.
- Analytical Method in Conduction Heat Transfer Myers, M.N.
- Theory and Design of Modern Pressure Vessels(2nd ed.) Harvey, J.F.
- ASME Boiler and Pressure Vessel Code, Section XI, Appendix A ASME
- Journal of the Computational Structural Engineering Institute of Korea v.9 no.2 Development of Structural Integrity Evaluation Program for Reactor Vessel under Pressurized Thermal Shock Jhung, M.J.
- Structural Engineering and Mechanics v.8 no.1 Deterministic Structural and Fracture Mechanics Analyses of Reactor Pressure Vessel for Pressurized Thermal Shock Jhung, M. J.;Park, Y.W.
- ASME Boiler and Pressure Vessel Code, Section XI, Appendix G ASME
- Regulatory Guide 1.99, Rev.2 Radiation Embrittlement of Reactor Vessel Materials USNRC
- Nuclear Engineering and Design v.51 Application of Warm Prestressing Effects to Fracture Mechanics Analyses of Nuclear Reactor Vessels during Severe Thermal Shock McGowan, J. J.
- PTSE-1, ORNL/PTSE-1, ORNL Quick-look Report on the First Pressurized Thermal Shock Test Bryan, R.H.(et al.)
- KAERI CR-005-94 Integrity Assessment of Kori Unit 1 RPV for Low Upper Shelf Toughness KAERI
- 10CFR50.61 Fractur Toughness Requirements for Protection against Pressurized Thermal Shock Events USNRC