62 citations · 99 across the 3 of their papers we have counts for
7 papers
Calculation and Verification of Irradiation Damage Cross Section with Energy-Angular Distribution
Shengli Chen, David Bernard, Pierre Tamagno +1
To complete the computation of Displacements per Atom (DPA) cross sections, the present work shows the methods of calculating DPA cross sections with the nuclear data of energy-ang…
Calculation and verification of neutron irradiation damage with differential cross sections
Shengli Chen, David Bernard, Pierre Tamagno +4
The Displacement per Atom (DPA) rate is conventionally computed with DPA cross sections in reactor applications. The method of direct calculation with energy-angular distributions…
Neutronic Study of UO2-BeO Fuel with Various Claddings
Shengli Chen, Cenxi Yuan
The neutronic properties of UO2-BeO fuel with various claddings are investigated through the Monte Carlo method and the Linear Reactivity Model. A second order polynomial function…
Minor Actinides Transmutation in Candidate Accident Tolerant Fuel-Claddings U3Si2-FeCrAl and U3Si2-SiC
Shengli Chen, Cenxi Yuan
An advanced transmutation method is suggested that the long-lived Minor Actinides (MAs) in the spent fuel can be efficiently transmuted in the candidate Accident Tolerant Fuel (ATF…
Radial Distributions of Power and Isotopic Concentrations in Candidate Accident Tolerant Fuel U3Si2 and UO2/U3Si2 Fuel Pins with FeCrAl Cladding
Shengli Chen, Cenxi Yuan, Daxi Guo
Monte Carlo simulations show similarity on radial distributions of power and isotopic concentrations at any effective full power depletion time among five kinds of fuel-cladding co…
Neutronic Analysis on Potential Accident Tolerant Fuel-Cladding Combination USi-FeCrAl
Shengli Chen, Cenxi Yuan
Neutronic performance is investigated for a potential accident tolerant fuel (ATF),which consists of USi fuel and FeCrAl cladding. In comparison with current UO-Zr syst…