1. Increased ductility in high velocity electromagnetic ring expansion;Altynova;Metall. Mater. Trans. A,1996
2. Bai, J., Prioul, C., Pelchat, J., Barcelo, F., 1991. Effects of Hydrides on the Ductile Brittle Transition in Stress-Relieved, Recrystallized and β-Treated Zircaloy-4, Proceedings of the International Topical Meeting on LWR Fuel Performance. American Nuclear Society, La Grange Park, IL, pp. 233–251.
3. Chow, C.K., Coleman, C.E., Hosbons, R.R., Davies, P.H., Griffiths, M., Choubey, R., 1991. Fracture toughness of irradiated Zr-2.5Nb pressure tubes from CANDU reactors. In: Eucken, C.M., Garde, A.M. (Eds.), Zirconium in the Nuclear Industry: Ninth International Symposium, ASTM STP 1132, American Society for Testing and Materials, Philadelphia, PA, pp. 246–275.
4. Chung, H.M., Kassner, T.F., 1980. Embrittlement Criteria for Zircaloy Fuel Cladding Applicable to Accident Situations in Light-Water Reactors: Summary Report. NUREG/CR-1344, ANL-79-48, Argonne National Laboratory.
5. Chung, H.M., 1987. Phase transformations in neutron-irradiated zircaloys. In: Garner, F.A., Packan, N.H., Kumar, A.S. (Eds.), Radiation-Induced Changes in Microstructure: Thirteenth International Symposium, ASTM STP 955, American Society for Testing and Materials, Philadelphia, PA, pp. 676–699.