62 citations · 99 across the 3 of their papers we have counts for
5 papers · 1 filter
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…
Study of Minor Actinides Transmutation in PWR MOX fuel
Shengli Chen, Cenxi Yuan, Jingxia Wu +1
The management of long-lived radionuclides in spent fuel is a key issue to achieve the closed nuclear fuel cycle and the sustainable development of nuclear energy. Partitioning-Tra…