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Featured researches published by Zhouyu Liu.


Journal of Nuclear Science and Technology | 2018

The pseudo-resonant-nuclide subgroup method based global–local self-shielding calculation scheme

Zhouyu Liu; Qingming He; Tiejun Zu; Liangzhi Cao; Hongchun Wu; Qian Zhang

ABSTRACT The pseudo-resonant-nuclide subgroup method (PRNSM) based global–local self-shielding calculation scheme is proposed to simultaneously resolve the local self-shielding effects (including spatial self-shielding effect and the resonance interference effect) for large-scale problems in reactor physics calculations. This method splits self-shielding calculation into global calculations and local calculations. The global calculations obtain the Dancoff correction factor for each pin cell by neutron current method. Then an equivalent one-dimensional (1D) cylindrical problem for each pin cell is isolated from the lattice system by preserving Dancoff correction factor. The local calculation is to perform self-shielding calculations of the equivalent 1D cylindrical problem by the PRNSM. The numerical results show that PRNSM obtains accurate spatial dependent self-shielded cross sections and improves the accuracy of dealing with the resonance interference over the conventional Bondarenko iteration method and the resonance interference factor method. Furthermore, because both global and local calculation is linearly proportional to the size of problems, the global–local calculation scheme could be applied to large-scale problems.


International Confernece Pacific Basin Nuclear Conference | 2016

Development and Validation of Subchannel Code SUBSC

Jun Chen; Liangzhi Cao; Chuanqi Zhao; Hongchun Wu; Zhouyu Liu

SUBSC was developed to simulate thermal–hydraulic phenomena in the core of pressurized water reactors, as well as innovative reactors operated with supercritical water as coolant. Both precise IAPWS-IF97 formulations and approximating polynomial correlations were implemented to calculate properties of water. A typical PWR fuel assembly problem, a supercritical water heat transfer experiment, and the steady state bundle benchmark of the pressurized water reactor subchannel and bundle tests (PSBT) were applied to validate this code. The SUBSC predicted results showed good agreement with experimental data and results obtained from COBRA, demonstrating feasibility and accuracy of this code. In order to improve efficiency, a restarted GMRES algorithm with preconditioning was implemented for solving the pressure correction equation. The numerical results showed the efficiency could be enhanced dramatically as the size of the problem being solved became large.


Nuclear Engineering and Technology | 2013

SCATTERING CORRECTION FOR IMAGE RECONSTRUCTION IN FLASH RADIOGRAPHY

Liangzhi Cao; Mengqi Wang; Hongchun Wu; Zhouyu Liu; Yuxiong Cheng; Hongbo Zhang

Scattered photons cause blurring and distortions in flash radiography, reducing the accuracy of image reconstruction significantly. The effect of the scattered photons is taken into account and an iterative deduction of the scattered photons is proposed to amend the scattering effect for image restoration. In order to deduct the scattering contribution, the flux of scattered photons is estimated as the sum of two components. The single scattered component is calculated accurately together with the uncollided flux along the characteristic ray, while the multiple scattered component is evaluated using correction coefficients pre-obtained from Monte Carlo simulations.The arbitrary geometry pretreatment and ray tracing are carried out based on the customization of AutoCAD. With the above model, an Iterative Procedure for image restORation code, IPOR, is developed. Numerical results demonstrate that the IPOR code is much more accurate than the direct reconstruction solution without scattering correction and it has a very high computational efficiency.


Annals of Nuclear Energy | 2011

A new three-dimensional method of characteristics for the neutron transport calculation

Zhouyu Liu; Hongchun Wu; Liangzhi Cao; Qichang Chen; Yunzhao Li


Progress in Nuclear Energy | 2017

Leakage reconstruction method for 2D/1D fusion transport calculations

Liang Liang; Zhouyu Liu; Youqi Zheng; Liangzhi Cao; Hongchun Wu


International Conference on Mathematics and Computational Methods Applied to Nuclear Science and Engineering, M and C 2013 | 2013

Parallel 3-D method of characteristics in MPACT

Brendan Kochunas; Thomas J. Dovvnar; Zhouyu Liu


Progress in Nuclear Energy | 2018

Development and verification of the high-fidelity neutronics and thermal-hydraulic coupling code system NECP-X/SUBSC

Zhouyu Liu; Jun Chen; Liangzhi Cao; Chen Zhao; Qingming He; Hongchun Wu


International Conference on Mathematics and Computational Methods Applied to Nuclear Science and Engineering, M and C 2013 | 2013

The method of modular characteristic direction probabilities in MPACT

Zhouyu Liu; Brendan Kochunas; Benjamin Collins; Thomas J. Downar; Hongchun Wu


Annals of Nuclear Energy | 2018

A new high-fidelity neutronics code NECP-X

Jun Chen; Zhouyu Liu; Chen Zhao; Qingming He; Tiejun Zu; Liangzhi Cao; Hongchun Wu


Progress in Nuclear Energy | 2018

Improvement and optimization of the pseudo-resonant-nuclide subgroup method in NECP-X

Zhouyu Liu; Qingming He; Xingjian Wen; Tiejun Zu; Linagzhi Cao; Hongchun Wu

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Hongchun Wu

Xi'an Jiaotong University

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Liangzhi Cao

Xi'an Jiaotong University

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Jun Chen

Xi'an Jiaotong University

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Chen Zhao

Xi'an Jiaotong University

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Qingming He

Xi'an Jiaotong University

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Yunzhao Li

Xi'an Jiaotong University

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Liang Liang

Xi'an Jiaotong University

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