Verification of OpenMC for fast reactor physics analysis with China experimental fast reactor start-up tests by Hui Guo, Xingkai Huo, Kuaiyuan Feng, Hanyang Gu

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Influence of nuclear data library on neutronics benchmark of China experimental fast reactor start-up tests by Hui Guo, Xin Jin, Xingkai Huo, Hanyang Gu, Haicheng Wu

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Optimization of the TRISO fuel particle distribution based on octahedral and icosahedral-based segmentation methods in the pebble-bed nuclear core by Maolong Liu, Chen Zeng, Zilin Luo, Hanyang Gu, Jian Deng

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Development and evaluation of fuel performance analysis code FuSPAC by Tenglong Cong, Hao Chen, Chao Chen, Shaohong Zhang, Hanyang Gu

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Development and verification of a Monte Carlo two-step method for lead-based fast reactor neutronics analysis by Yiwei Wu, Qufei Song, Ruixiang Wang, Yao Xiao, Hanyang Gu, Hui Guo

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Multigroup cross-sections generated using Monte-Carlo method with flux-moment homogenization technique for fast reactor analysis by Yiwei Wu, Qufei Song, Kuaiyuan Feng, Jean-François Vidal, Hanyang Gu, Hui Guo

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Multiphysics analysis of a metal hydride moderated megawatt heat pipe reactor with burnable poisons by KuaiYuan Feng, Jipu Hu, Yihu Wang, Tenglong Cong, Hanyang Gu, Hui Guo

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