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Publications by Cenxi Yuan
Neutronic Analysis on Potential Accident Tolerant Fuel-Cladding Combination U3Si2-FeCrAl
Science and Technology of Nuclear Installations
Engineering
Nuclear Energy
Formation of Two-Neutron Halo in Drip-Line Nuclei From the Low-Energy Neutron-Neutron Interaction
Related publications
Assessment of Neutronic Characteristics of Accident-Tolerant Fuel and Claddings for CANDU Reactors
Science and Technology of Nuclear Installations
Engineering
Nuclear Energy
Alloy Selection for Accident Tolerant Fuel Cladding in Commercial Light Water Reactors
Metallurgical and Materials Transactions E
Assessment of Corrosion Resistance of Candidate Alloys for Accident Tolerant Fuel Cladding Under Reactor Conditions
Microscopy and Microanalysis
Instrumentation
Burst Strength of Copper Barrier Fuel Cladding During Postulated Loss-Of-Coolant Accident.
Journal of Nuclear Science and Technology
High Energy Physics
Nuclear
Engineering
Nuclear Energy
Study of the Dependence of the Cladding – Fuel Pellet Gap Conductance Coefficient on the Fuel Burn-Up and the Effects on the Neutronic Characteristics of the Reactor Core
Izvestiya Wysshikh Uchebnykh Zawedeniy, Yadernaya Energetika
Engineering
Nuclear Energy
Accident Tolerant Materials for LMFR
Potential Corrosion and Degradation Mechanisms of Zircaloy Cladding on Spent Nuclear Fuel in a Tuff Repository
Pellet-Cladding Interaction on Light Water Reactor Fuel, (I)
Journal of the Atomic Energy Society of Japan / Atomic Energy Society of Japan
Effect of Power Cycling on LMFBR Fuel-Cladding Behavior.
