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Chinese Physics C | 2014

Preliminary study on CAD-based method of characteristics for neutron transport calculation

Chen Zhenping; Zheng Huaqing; Sun Guangyao; Song Jing; Hao Lijuan; Hu Liqin; Wu Yican

The method of characteristics (MOC) is widely used for neutron transport calculation in recent decades. However, the key problem determining whether MOC can be applied in highly heterogeneous geometry is how to combine an effective geometry modeling method with it. Most of the existing MOC codes conventionally describe the geometry model just by lines and arcs with extensive input data. Thus they have difficulty in geometry modeling and ray tracing for complicated geometries. In this study, a new method making use of a CAD-based automatic modeling tool MCAM which is a CAD/Image-based Automatic Modeling Program for Neutronics and Radiation Transport developed by FDS Team in China was introduced for geometry modeling and ray tracing of particle transport to remove those limitations. The diamond-difference scheme was applied to MOC to reduce the spatial discretization errors of the flat flux approximation. Based on MCAM and MOC, a new MOC code was developed and integrated into SuperMC system, which is a Super Multi-function Computational system for neutronics and radiation simulation. The numerical results demonstrated the feasibility and effectiveness of the new method for neutron transport calculation in MOC.Our new method makes use of a CAD-based automatic modeling tool, MCAM, for geometry modeling and ray tracing of particle transport in method of characteristics (MOC). It was found that it could considerably enhance the capability of MOC to deal with more complicated models for neutron transport calculation. In our study, the diamond-difference scheme was applied to MOC to reduce the spatial discretization errors of the flat flux approximation. Based on MCAM and MOC, a new 2D MOC code was developed and integrated into the SuperMC system, which is a Super Multi-function Computational system for neutronics and radiation simulation. The numerical results demonstrated the feasibility and effectiveness of the new method for neutron transport calculation in MOC.


Archive | 2015

Radiation shielding calculation method based on monte carlo self-adaptive variance reduction

Zheng Huaqing; Song Jing; Sun Guangyao; Hao Lijuan; Wu Yican


Archive | 2013

Monte Carlo simulation method for moving body dose based on data field segmentation

Song Jing; Zheng Huaqing; Long Pengcheng; Hao Lijuan; Wu Yican


Archive | 2018

Hybrid Monte Carlo and Deterministic Particle Transport Method Based on Transition Area

Wu Yican; Hu Liqin; Long Pengcheng; Hao Lijuan; Song Jing


Archive | 2017

Transition region based Monte Carlo and certainty theory coupled particle transport method

Wu Yican; Hu Liqin; Long Pengcheng; Hao Lijuan; Song Jing


Archive | 2017

Efficient source sampling method for irregular geometry based on spatial segmentation in kernel simulation analysis

Zheng Xiaolei; Wu Bin; Yu Shengpeng; Hao Lijuan; Song Jing


Archive | 2017

Rapid nuclear cross section Doppler broadening method

Hao Lijuan; Wu Yican; Hu Liqin; Song Jing; Sun Guangyao


Archive | 2017

Continuous-energy-point Monte Carlo particle transport method based on multi-group virtual sections

Hao Lijuan; Wu Yican; Hu Liqin; Song Jing; Sun Guangyao


Archive | 2017

Whole energy spectrum neutron radiation damage precise simulation system and algorithm thereof

Zou Jun; Wu Yican; Hu Liqin; Hao Lijuan; Shang Leiming


Archive | 2017

Monte-carlo-particle-transport rapid geometric processing method based on characteristic length

Wang Lei; Hao Lijuan; Yu Shengpeng; He Peng; Sun Guangyao; Wu Bin; Hu Liqin

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Song Jing

University of Science and Technology of China

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Wu Yican

Chinese Academy of Sciences

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Hu Liqin

Chinese Academy of Sciences

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Sun Guangyao

University of Science and Technology of China

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Zheng Huaqing

Chinese Academy of Sciences

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Long Pengcheng

Chinese Academy of Sciences

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Wu Bin

Chinese Academy of Sciences

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Chen Chaobin

Chinese Academy of Sciences

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Chen Zhenping

University of Science and Technology of China

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Cheng Mengyun

Chinese Academy of Sciences

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