Search Results - "Kuaiyuan Feng"

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

“…High-fidelity nuclear data libraries and neutronics simulation tools are essential for the development of fast reactors. The IAEA coordinated research project…”
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Multigroup cross-sections generated using Monte-Carlo method with flux-moment homogenization technique for fast reactor analysis by Wu, Yiwei, Song, Qufei, Feng, Kuaiyuan, Vidal, Jean-François, Gu, Hanyang, Guo, Hui

“…The development of fast reactors with complex designs and operation status requires more accurate and effective simulation. The Monte-Carlo method can generate…”
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Multiphysics analysis of a metal hydride moderated megawatt heat pipe reactor with burnable poisons by Feng, KuaiYuan, Hu, Jipu, Wang, Yihu, Cong, Tenglong, Gu, Hanyang, Guo, Hui

“…With the development of nuclear energy, microreactors have received increasing interest among researchers in recent years. In this paper, a megawatt heat pipe…”
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Neutronics modelling of control rod compensation operation in small modular fast reactor using OpenMC by Guo, Hui, Peng, Xingjie, Wu, Yiwei, Jin, Xin, Feng, Kuaiyuan, Gu, Hanyang

“…The small modular liquid-metal fast reactor (SMFR) is an important component of advanced nuclear systems. SMFRs exhibit relatively low breeding capability and…”
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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-Francois Vidal, Hanyang Gu, Hui Guo

“…The development of fast reactors with complex designs and operation status requires more accurate and effective simulation. The Monte-Carlo method can generate…”
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Preliminary analysis of a zirconium hydride moderated megawatt heat pipe reactor by Feng, Kuaiyuan, Wu, Yiwei, Hu, Jipu, Jin, Xin, Gu, Hanyang, Guo, Hui

“…•A moderated megawatt-class HPR core design is proposed and the influence of moderators is analyzed.•The moderators can reduce the fuel loading and shield…”
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Development and verification of an MC/MOC two-step scheme for neutronic analysis of FCM-fueled micro gas-cooled reactor by Feng, Kuaiyuan, Song, Qufei, Shen, Yuyang, Lou, Lei, Xiao, Yao, Guo, Hui, Gu, Hanyang

“…•An MC/MOC two-step scheme is developed and verified for FCM-fueled gas-cooled microreactors.•The fuel and structure multi-group cross-sections are generated…”
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Numerical study on the neutronics-thermal-mechanics coupling characteristics of the heat pipe nuclear reactor core by Wang, Yihu, Feng, Kuaiyuan, Wu, Yiwei, Liu, Limin, Guo, Hui, Cong, Tenglong, Gu, Hanyang

“…•A numerical simulation method for neutronics-thermal-mechanics field of a heat pipe nuclear reactor is developed with open source codes.•The two-way coupling…”
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Multi-objective optimization of method of characteristics parameters based on genetic algorithm by Song, Qufei, Zhang, Chang, Wu, Yiwei, Feng, Kuaiyuan, Guo, Hui, Gu, Hanyang

“…Method of Characteristics (MOC) is a transport-solving method with high numerical accuracy and geometric flexibility, but it is computationally intensive…”
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Time-dependent neutron transport method based on three-dimensional method of characteristics by Song, Qufei, Zhang, Chang, Wu, Yiwei, Feng, Kuaiyuan, Guo, Hui, Gu, Hanyang

“…The 3D Method of Characteristics (MOC) has high numerical accuracy, geometrical flexibility, making it suitable for the simulation of advanced reactors with…”
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Preliminary verification of multi-group cross-sections generation and locally heterogeneous transport calculation using OpenMC with CEFR start-up tests benchmark by Guo, Hui, Wu, Yiwei, Jin, Xin, Feng, Kuaiyuan, Huo, Xingkai, Gu, Hanyang

“…The multi-group (MG) Monte-Carlo (MC) scheme is a hybrid method based on MC solvers and deterministic strategies. This paper focuses on the study of MG schemes…”
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小型模块化快堆中含铪控制棒的设计与分析 by 郭辉, 冯快源, 顾汉洋

“…TL371; 快堆一般采用以碳化硼(B4 C)为吸收剂的控制棒进行反应性控制.小型模块化快堆中子泄漏率较大,增殖能力偏弱,单位燃耗反应性损失较大.模块化反应堆运行周期较长,且需要紧凑型堆芯设计,控制棒数量有限.因此,小型模块化快堆需要高10 B富集度的B4…”
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