1. Fuel behavior under loss-of-coolant accident situations;Chung;Nucl. Eng. Technol.,2005
2. D.O. Hobson and P. L. Rittenhouse, Embrittlement of zircaloy clad fuel rods by steam during LOCA Transients, ORNL-4758, Oak Ridge National Laboratory, January 1972.
3. Ductile-brittle behavior of zircaloy fuel cladding;Hobson,1973
4. USNRC Regulatory Guide 1.224. Preliminary Draft (Draft was issued as DG-1263, dated March 2014), Establishing Analytical Limits for Zirconium-Alloy Cladding Material, Washington, (2018) 1–32.
5. USNRC. Regulatory Guide 1.223–Determining post quench ductility, Washington. D.C., USA, 2015.