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Comparison of neutronic aspects in high-temperature gas-cooled reactor using ZrC and SiC Triso particle with 50 and 100 MWt powerINTERNATIONAL JOURNAL OF ENERGY RESEARCHIF4.22021-11-225OA
Initial core design analysis of lead (208) -bismuth eutectic-cooled reactor with radial fuel shufflingINTERNATIONAL JOURNAL OF ENERGY RESEARCHIF4.22021-02-063OAAI
Neutronic analysis of sodium-cooled fast reactor design with different fuel types using modified CANDLE shuffling strategy in a radial directionINTERNATIONAL JOURNAL OF ENERGY RESEARCHIF4.22021-01-251OAAI
Reflector materials selection for core design of modular gas-cooled fast reactor usingOpenMCcodeINTERNATIONAL JOURNAL OF ENERGY RESEARCHIF4.22020-10-1412OAAI
Comparison of uranium plutonium nitride (U-Pu-N) and thorium nitride (Th-N) fuel for 500 MWth gas-cooled fast reactor (GFR) long life without refuelingINTERNATIONAL JOURNAL OF ENERGY RESEARCHIF4.22017-10-209OAAI
Void reactivity aspect and fuel conversion potential of heavy water cooled thorium reactorINTERNATIONAL JOURNAL OF ENERGY RESEARCHIF4.22016-07-207OAAI
Reactor core and actinide production evaluation based on different loading material of recyled spent nuclear fuel of LWR in FBR基于FBR中LWR回收废核燃料不同装载材料的反应堆堆芯和act系元素生产评估INTERNATIONAL JOURNAL OF HYDROGEN ENERGYIF8.32016-05-0111PREAI
Influence of void fraction on BWR spent fuel direct recycling scenarioINTERNATIONAL JOURNAL OF HYDROGEN ENERGYIF8.32015-11-012PREAI
Preliminary study on plutonium and minor actinides utilization in thorims-nes minifuji reactorENERGY CONVERSION AND MANAGEMENTIF10.92013-08-0121PRE
Study on material attractiveness aspect of spent nuclear fuel of LWR and FBR cycles based on isotopic plutonium productionENERGY CONVERSION AND MANAGEMENTIF10.92013-08-016PRE
Effect of void-fraction on characteristics of several thorium fuel cycles in BWRENERGY CONVERSION AND MANAGEMENTIF10.92012-11-016PREAI
Reactor core design optimization of the 200 MWt Pb-Bi cooled fast reactor for hydrogen productionPROGRESS IN NUCLEAR ENERGYIF3.22008-03-015PREAI
Simulation study of steels corrosion phenomenon in liquid lead-bismuth cooled reactors using molecular dynamics methodsPROGRESS IN NUCLEAR ENERGYIF3.22008-03-0120PREAI
Neutronic performance comparation of MOX, nitride and metallic fuel based 25-100 MWe Pb-Bi cooled long life fast reactors without on-site refuellingPROGRESS IN NUCLEAR ENERGYIF3.22008-03-0111PREAI
Safety performance comparation of MOX, nitride and metallic fuel based 25-100 MWe Pb-Bi cooled long life fast reactors without on-site refuellingPROGRESS IN NUCLEAR ENERGYIF3.22008-03-0110PREAI
Influence of void fraction change on plutonium and minor actinides recycling in BWR with equilibrium burnupPROGRESS IN NUCLEAR ENERGYIF3.22008-03-0110PREAI
The utilization of thorium for long-life small thermal reactors without on-site refuelingPROGRESS IN NUCLEAR ENERGYIF3.22008-03-019PREAI
Design and safety optimization of ship-based small nuclear power reactorsPROGRESS IN NUCLEAR ENERGYIF3.22008-03-0110PREAI
The prospect of MOX fuel based Pb-Bi cooled small nuclear power reactorsPROGRESS IN NUCLEAR ENERGYIF3.22005-01-0111PREAI
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