Fracture mechanics concepts for evaluation of irradiated reactor pressure vessel material behavior

MLA

J. Föhl, et al. “Fracture Mechanics Concepts for Evaluation of Irradiated Reactor Pressure Vessel Material Behavior.” Nuclear Engineering and Design, vol. 190, June 1999, pp. 83–95. EBSCOhost, https://doi.org/10.1016/s0029-5493(98)00314-8.

APA

J. Föhl, H. Beyer, & K. Kussmaul. (1999). Fracture mechanics concepts for evaluation of irradiated reactor pressure vessel material behavior. Nuclear Engineering and Design, 190, 83–95. https://doi.org/10.1016/s0029-5493(98)00314-8

Chicago

J. Föhl, H. Beyer, and K. Kussmaul. 1999. “Fracture Mechanics Concepts for Evaluation of Irradiated Reactor Pressure Vessel Material Behavior.” Nuclear Engineering and Design 190 (June): 83–95. doi:10.1016/s0029-5493(98)00314-8.