Results 241 to 250 of about 4,286 (261)

Zircaloy-4 Cladding Embrittlement due to Inner Surface Oxidation under Simulated Loss-of-Coolant Condition

Journal of Nuclear Science and Technology, 1981
Hiroshi Uetsuka, Teruo Furuta, Satoru Kawasaki   +2 more
exaly  

Safety Evaluation of Silicon Carbide and Zircaloy-4 Cladding during a Large-Break Loss-of-Coolant Accident

Energies, 2018
Kyohun Joo, Sung-Pil Park, Kwangwon Ahn   +2 more
exaly  

Numerical Investigation of a Channel During Loss of Coolant Accident

2023
Bhuwanesh Kumar, Ravi Kumar, Akhilesh Gupta   +2 more
openaire   +1 more source

Thermal analysis of heated cylinder simulating nuclear reactor during loss of coolant accident

Journal of Nuclear Science and Technology, 2014
Hirofumi Ohashi, Hiroyuki Sato, Masuro Ogawa   +2 more
exaly  

Analysis of accidental loss of pool coolant due to leakage in a PWR SFP

Annals of Nuclear Energy, 2015
Wenxi Tian, , Yapei Zhang
exaly  

Using Kernel Density Estimation to Detect Loss-of-Coolant Accidents in a Pressurized Water Reactor

Nuclear Technology, 2019
Jacob Farber, Daniel Cole, Vaibhav Yadav   +2 more
exaly  

Behavior of an improved Zr fuel cladding with oxidation resistant coating under loss-of-coolant accident conditions

Journal of Nuclear Materials, 2016
Jae Ho Yang, Dong Jun Park
exaly  

Zircaloy-Clad Fuel Rod Burst Behavior under Simulated Loss-of-Coolant Condition in Pressurized Water Reactors

Journal of Nuclear Science and Technology, 1978
Teruo Furuta, Satoru Kawasaki
exaly  

Boiling Water Reactor Loss-of-Coolant Tests with Two Bundle Loop

Journal of Nuclear Science and Technology, 1984
Seihiro Itoya, Fujio Masuda
exaly  

Analyses for Passive Safety of Fusion Reactor during Ex-Vessel Loss of Coolant Accident

Journal of Nuclear Science and Technology, 1995
Tomoaki Kunugi, Yasushi Seki, Takuro Honda   +2 more
exaly