教育背景

博士学位    201306    清华大学    核科学与技术
学士学位    200806    上海交通大学    核工程与技术

工作履历

202310 - 至今    清华大学核研院    103室副主任

202206 - 至今    清华大学核研院    长聘副教授

201806-202206    清华大学核研院    准聘副教授

201307-201806    清华大学核研院    助理研究员、助理教授

学术兼职

202411 - 至今    中国核学会研究堆与新堆分会秘书长

202208 - 至今    《Nuclear Science and Techniques》青年编委

201901 - 至今    全国蒙特卡罗方法及其应用专委会委员

研究领域

反应堆物理设计与数值计算
先进反应堆自主设计软件研发

研究概况

2023 - 至今    宽能谱超高通量试验堆软件设总、屏蔽物理设计负责人

2016 - 至今    高温气冷堆物理热工源项软件负责人

2016 - 至今    一体化自然循环反应堆中子源及物理启动设计负责人

2022 - 2025   高温气冷堆随机燃耗历史效应研究与实验验证    中核集团青年英才项目

2020 -2022    高温气冷堆三维物理分析方法研究与功能开发    中核集团青年英才项目

2019 - 2020      高温气冷堆堆芯设计与系统分析自主化软件研发及验证    国家科技重大专项课题

2017 - 2020      HTR-10超高温运行研究与安全分析    国家科技重大专项课题

奖励与荣誉

2022    清华大学“学术新人奖”

2018    中国核能行业协会科学技术奖创新团队奖

2013    清华大学优秀博士学位论文

学术成果

近五年发表学术论文：

[1] Zhang H, Tan B, She D*, Shi L. An efficient method for solving flow field in high temperature gas-cooled reactor. Progress in Nuclear Energy, 2025, 180:105599.

[2] Liang Z, She D*, Wen Y, Shi L, Zhang Z. Generalized Hébert method for double-heterogeneity problem. Progress in Nuclear Energy, 2025, 180:105573.

[3] Wu H, Wen Y, Xia B, She D*, Zhang Z. A new fuel shuffling model for treating the random burnup histories of pebble-bed reactor. Progress in Nuclear Energy, 2025, 180:105571.

[4] Fu B, Zhang L R, She D*, et al. XPZLIB: an HDF5-format multi-group cross-section library [J]. Nuclear Science and Techniques, 2024, 35(11): 1-15.

[5] Liang Z, She D*, Wen Y, et al., Chord length sampling correction analysis for dispersion fuel in Monte Carlo simulation [J]. Nuclear Science and Techniques, 2024 (35):71.

[6] Liang Z, She D*, Wen Y, et al. Improved Collision Probability Analysis of the Double-Heterogeneity Problem Based on Matrix Chord Length Correction [J]. Nuclear Science and Engineering, 2024: 1-13.

[7] Wen Y, She D*, Shi L .Improvement of cylindrical nodal expansion method for treating HTGR void cavity [J]. Progress in Nuclear Energy, 161, 104714, 2023.

[8] Wen Y, She D*, Shi L. Improved methods for calculating the neutron diffusion coefficient of general pebble bed [J]. Nuclear Science and Engineering, 2023 (197): 2920-2934.

[9] Wen Y, She D*, Shi L. The progress on the 3D whole-core neutronics calculation of PANGU code [J]. Nuclear Engineering and Design, 2022, 398: 111962.

[10] Wen Y, She D*, Shi L. An improved homogenization method for the treatment of strong absorbers in pebble-bed HTGR [J]. Annals of Nuclear Energy, 2022, 170(2-3):108983.

[11] Li J, She D*, Shi L, et al. Development and validation of FRAT code for coated particle fuel failure analysis [J]. Nuclear Engineering and Technology [J], 2022, 54(11): 4049-4061.

[12] Zhang T*, She D, Zhang Q, et al. Reactor Physics: Methods and Applications [J]. Frontiers in Energy Research, 2022: 824.

[13] Li J, Sun J, She D*, et al. Influence of input data uncertainties on failure probability of TRISO-coated particle [J]. Annals of Nuclear Energy, 2021, 163: 108561.

[14] Wen Y, She D*, Shi L. The neutron streaming correction method in the homogenization of Pebble-bed HTGR reflector [J]. Annals of Nuclear Energy, 2021, 162: 108531.

[15] Li J, She D*, Shi L. A comparison study on mechanical models for TRISO fuel particle in HTGR [J]. Annals of Nuclear Energy, 2021: 108484.

[16] She D, Xia B, Guo J*, et al. Prediction calculations for the first criticality of the HTR-PM using the PANGU code [J]. Nuclear Science and Techniques, 2021, 32(9): 1-7.

[17] She D, Chen F, Xia B*, et al. Simulation of the HTR-10 operation history with the PANGU code [J]. Frontiers in Energy Research, 2021, 9: 302.