Results 111 to 115 of about 167,510,152 (115)

Investigation of the RCS-containment integral effect test on intermediate and small break loss-of-coolant accident (LOCA) transients

Annals of Nuclear Energy
Kyoung-Ho Kang, Seok Cho
exaly  

Realistic performance assessment of FeCrAl-UN/USi accident tolerant fuel under loss-of-coolant accident scenario

Reliability Engineering and System Safety
Qingwen Xiong, Yiliu Liu, Zhifang Qiu
exaly  

Loss of coolant accident diagnosis for large pressurized water reactors based on long short-term memory network

Annals of Nuclear Energy
Wenlong Liang
exaly  

Development and validation of Loss of Coolant Accident (LOCA) simulation capability in the ENIGMA fuel performance code for zirconium-based cladding materials

Nuclear Engineering and Design
Aiden Peakman
exaly  

Zircaloy Fuel Cladding Behavior in a Loss-of-Coolant Accident: A Review

1987
exaly