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Scientific Research
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Transverse mixing characteristics of single-phase flow in the helical cruciform fuel assembly.Annals of Nuclear Energy.2023
Preliminary thermal and mechanical analysis on the reactor core of a new heat pipe cooled reactor applied in the underwater environment.Progress in Nuclear Energy.2022
Investigation of the safety limits and the limiting safety system settings on a super carbon-dioxide cooled micro modular reactor.Annals of Nuclear Energy.2023
Verification of OpenMC for fast reactor physics analysis with China experimental fast reactor start-up tests.Nuclear Engineering and Technology.2022
Influence of nuclear data library on neutronics benchmark of China experimental fast reactor start-up tests.Nuclear Engineering and Technology.2022
Preliminary analysis of a zirconium hydride moderated megawatt heat pipe reactor.Nuclear Engineering and Design.2022
Neutronic modeling of megawatt-class heat pipe reactors.ANNALS OF NUCLEAR ENERGY.2021
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颗粒燃料堆芯蒙卡多群截面产生及局部非均匀计算方法研究
基于局部慢化能谱的长寿期小型快堆可燃毒物补偿控制特性研究
非均匀加热棒联合研制技术服务合同
兆瓦级热管冷却反应堆堆芯基础研究
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