Author:
Baker Una,Choi Yong-Joon,Rollins Nicholas,Nguyen Khang,Jung WooHyun,Whitmeyer Abe,Hou Jason,Lindley Ben
Reference86 articles.
1. § 50.67 Accident source term., NRC Web. Accessed: Feb. 23, 2024. [Online]. Available: https://www.nrc.gov/reading-rm/doc-collections/cfr/part050/part050-0067.html.
2. ANS Standards Committee, ‘Decay heat power in light water reactors’, Technical Report ANSI/ANS-5.1-1994, American Nuclear Society, USA, 1993.
3. Modelling FeCrAl cladding thermo-mechanical performance. part II: comparative analysis with zircaloy under LOCA conditions;Aragón;Prog. Nucl. Energy,2023
4. Fuel and fission product behaviour in early phases of a severe accident. part I: experimental results of the PHEBUS FPT2 test;Barrachin;J. Nucl. Mater.,2014
5. Strength and rupture geometry of un-irradiated C26M FeCrAl under LOCA burst testing conditions;Bell;J. Nucl. Mater.,2021