Search Results - "Song, Qufei"

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

“…With the rise of economic and safety standards for nuclear reactors, new concepts of Gen-IV reactors and modular reactors showed more complex designs that…”
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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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Generating multi-group cross-sections using continuous-energy Monte Carlo method for fast reactor analysis by Guo, Hui, Shen, Yuyang, Wu, Yiwei, Song, Qufei, Gu, Hanyang

“…The deterministic two-step method, comprising multigroup cross-section generation and core calculation, is widely applied in fast reactor design and analysis…”
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螺旋金属燃料多物理耦合分析方法与概念设计研究 by 顾汉洋, 肖瑶, 丛腾龙, 郭辉, 傅俊森, 蔡孟珂, 宋去非

“…TL32%O242;…”
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Development of OpenMC/Trivac two-step scheme for fast reactor core neutronics analysis by Guo, Hui, Wu, Yiwei, Song, Qufei, Cong, Tenglong, Gu, Hanyang

“…•An open-source two-step scheme coupling OpenMC and Trivac is developed and verified for fast reactor analysis.•The MC-generated multigroup cross-sections and…”
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Pareto front of sodium void worth and breeding ratio in metal-fueled sodium fast reactor with axially heterogeneous core design by coupling neutronics and genetic algorithm by Guo, Hui, Han, Shengtao, Jin, Xin, Wu, Yiwei, Song, Qufei, Xiao, Yao, Gu, Hanyang

“…•A coupling method for neutronics simulations and genetic algorithms is developed and applied to a 3000 MWth metallic SFR for optimizing sodium void worth,…”
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Reactivity control optimization of boron-free small modular pressurized water reactor with helical-cruciform metallic fuel by Zhang, Chang, Song, Qufei, Guo, Hui, Cong, Tenglong, Xiao, Yao, Gu, Hanyang

“…•A boron-free SMPWR core design with helical-cruciform metallic fuel is proposed.•The reactivity control optimizations of burnable absorbers and control rods…”
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Development of a design method for burnable poisons in small modular fast reactors by Wu, Yiwei, Shen, Yuyang, Jin, Xin, Song, Qufei, Xiao, Yao, Guo, Hui, Gu, Hanyang

“…•Develop a fast prediction method for burnable poison assemblies to evaluate the compensation ability of different designs.•Establish the Monte Carlo two-step…”
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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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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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Generating Multi-group Homogenized Cross-sections Using Continuous-energy Monte Carlo Method for Fast Reactor Analysis by GUO Hui, SHEN Yuyang, WU Yiwei, CHEN Cuilan, SONG Qufei, GU Hanyang

“…The deterministic two-step method for the fast reactor neutronics calculation, composed of cross-section homogenization and diffusion or transport core…”
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Multi-physics Analysis Method and Conceptual Design of Helically Metallic Fuel by GU Hanyang, XIAO Yao, CONG Tenglong, GUO Hui, FU Junsen, CAI Mengke, SONG Qufei

“…The helically metallic fuel is promising to improve the power density and safety margin of reactors core by its advantages of high thermal conductivity, large…”
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A tensor decomposition model for evaluating isotopic yield in neutron-induced fission by Song, Qufei, Zhu, Long, Su, Jun, Guo, Hui

“…After constructing yield tensors with three dimensions for 851 fission products and filling the tensors with the independent yield data from the ENDF/B-VIII.0…”
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