Personal information

Keywords

Neutron Transport, Nuclear Reactor Analysis, Advanced Nuclear Energy System

Countries

China

Activities

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Employment (1)

Xi'an Jiaotong University: Xi'an, CN

Employment
Source: Self-asserted source
Youqi Zheng

Education and qualifications (1)

Xi'an Jiaotong University: Xi'an, CN

Education
Source: Self-asserted source
Youqi Zheng

Works (16)

Extension of SARAX code system for reactors with intermediate spectrum

Nuclear Engineering and Design
2020-12 | Journal article
DOI: 10.1016/j.nucengdes.2020.110883
Contributors: Linfang Wei; Youqi Zheng; Xianan Du; Hongchun Wu
Source: check_circle
Crossref

Validation of SARAX code system using the SFR operational tests

Annals of Nuclear Energy
2020-11 | Journal article
DOI: 10.1016/j.anucene.2020.107744
Contributors: Xianan Du; Youqi Zheng; Yongping Wang; Zi'an Zhai; Hang Zhou
Source: check_circle
Crossref

A new hexagonal-Z nodal SN method in SARAX code system

Annals of Nuclear Energy
2020-09 | Journal article
DOI: 10.1016/j.anucene.2020.107546
Contributors: Yongping Wang; Zhitao Xu; Youqi Zheng; Hongchun Wu
Source: check_circle
Crossref

NECP-hydra: A high-performance parallel S code for core-analysis and shielding calculation

Nuclear Engineering and Design
2020-09 | Journal article
DOI: 10.1016/j.nucengdes.2020.110711
Contributors: Yongping Wang; Youqi Zheng; Longfei Xu; Liangzhi Cao
Source: check_circle
Crossref

Nuclear-data adjustment based on the continue-energy cross-section library for the fast reactor

Annals of Nuclear Energy
2020-08 | Journal article
DOI: 10.1016/j.anucene.2020.107453
Contributors: Chenghui Wan; Yihan Huang; Youqi Zheng; Liangzhi Cao; Hongchun Wu
Source: check_circle
Crossref

IFDF acceleration method with adaptive diffusion coefficients for SN nodal calculation in SARAX code system

Annals of Nuclear Energy
2020-02 | Journal article
DOI: 10.1016/j.anucene.2019.107056
Contributors: Zhitao Xu; Youqi Zheng; Yongping Wang; Hongchun Wu
Source: check_circle
Crossref

Improvement of few-group cross-section generation in fast reactor analysis system SARAX

Annals of Nuclear Energy
2019-10 | Journal article
DOI: 10.1016/j.anucene.2019.04.026
Contributors: Linfang Wei; Youqi Zheng; Hongchun Wu
Source: check_circle
Crossref

Validation of SARAX for the China Fast Reactor with the extrapolated experimental data

Annals of Nuclear Energy
2019-05 | Journal article
DOI: 10.1016/j.anucene.2018.12.009
Contributors: Chenghui Wan; Liang Qiao; Youqi Zheng; Liangzhi Cao; Hongchun Wu
Source: check_circle
Crossref

SARAX: A new code for fast reactor analysis part I: Methods

Nuclear Engineering and Design
2018-12 | Journal article
DOI: 10.1016/j.nucengdes.2018.10.008
Contributors: Youqi Zheng; Xianan Du; Zhitao Xu; Shencheng Zhou; Yong Liu; Chenghui Wan; Longfei Xu
Source: check_circle
Crossref

Transient analysis of MOX-3600 and MET-1000 sodium-cooled fast reactor using SARAX code system

Annals of Nuclear Energy
2018-11 | Journal article
DOI: 10.1016/j.anucene.2018.07.042
Contributors: Xianan Du; Youqi Zheng; Liangzhi Cao; Hongchun Wu
Source: check_circle
Crossref

Unstructured coarse mesh finite difference method to accelerate k-eigenvalue and fixed source neutron transport calculations

Annals of Nuclear Energy
2018-10 | Journal article
DOI: 10.1016/j.anucene.2018.05.044
Contributors: Shengcheng Zhou; Hongchun Wu; Liangzhi Cao; Youqi Zheng
Source: check_circle
Crossref

Hybrid MPI-communication for the multi-angular S N parallel sweep on 3-D regular grids

Annals of Nuclear Energy
2018-06 | Journal article
DOI: 10.1016/j.anucene.2018.03.003
Contributors: Longfei Xu; Liangzhi Cao; Youqi Zheng; Hongchun Wu
Source: check_circle
Crossref

SARAX: A new code for fast reactor analysis part II: Verification, validation and uncertainty quantification

Nuclear Engineering and Design
2018-05 | Journal article
DOI: 10.1016/j.nucengdes.2018.02.033
Contributors: Youqi Zheng; Liang Qiao; Zi'an Zhai; Xianan Du; Zhitao Xu
Source: check_circle
Crossref

Flexibility of ADS for minor actinides transmutation in different two-stage PWR-ADS fuel cycle scenarios

Annals of Nuclear Energy
2018-01 | Journal article
DOI: 10.1016/j.anucene.2017.08.037
Contributors: Shengcheng Zhou; Hongchun Wu; Youqi Zheng
Source: check_circle
Crossref

Assessment of transient characteristics of fast reactors and influences of minor actinides using neutron transport method

International Journal of Energy Research
2017-11-14 | Journal article
DOI: 10.1002/er.3781
Contributors: Mingtao He; Youqi Zheng; Hongchun Wu; Zhuo Li; Xianan Du
Source: check_circle
Crossref

Application of the virtual density theory in fast reactor analysis based on the neutron transport calculation

Nuclear Engineering and Design
2017-08 | Journal article
DOI: 10.1016/j.nucengdes.2017.05.020
Contributors: Youqi Zheng; Yunlong Xiao; Hongchun Wu
Source: check_circle
Crossref
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