游泳池式屏蔽试验反应堆

10兆瓦高温气冷实验反应堆

5兆瓦低温核供热反应堆

10兆瓦高温气冷实验反应堆主控制室

学术论文：

[1] HE X, YIN H, DU B, et al. High Temperature Corrosion Behavior of Inconel 617 in Environment of Impure Heli[J]. Yuanzineng Kexue Jishu/Atomic Energy Science and Technology, 2024,58(1): 189-197.

[2] DU B, ZHANG H, ZHENG W, et al. Carburization and tensile behavior of Alloy 617 in impure helium containing a part-per-million level of CH4 at 950 °C[J]. Corrosion Science, 2024,227.

[3] LIU R, LI H, ZHANG H, et al. Study on tritium permeation behavior in primary and second circuits of the hydrogen production system by methane steam reforming using HTGR[J]. Nuclear Engineering and Design, 2024,421.

[4] ZHANG H, ZHANG W, ZHANG L, et al. Estimation of transuranic isotopes in irradiated fuel elements for pebble bed HTR on activity vector[J]. Progress in Nuclear Energy, 2024,168.

[5] LI H, ZHENG W, DU B, et al. Study on Corrosion Behavior of T-22 Alloy in Ultrahigh Temperature Impure Helium and Air[C]//. Springer Proceedings in Physics, 2023: 1140-1148.

[6] ZHANG Y, FANG X, JIANG S, et al. The direct measurement of HTR-10 in-core neutron flux[J]. Nuclear Engineering and Design, 2023,401.

[7] ZHENG W, LI H, DU B, et al. High-temperature reaction kinetics of Inconel 617 in impure helium[J]. Nuclear Materials and Energy, 2023,34.

[8] ZHENG W, DU B, LI H, et al. High temperature corrosion of two superalloys in the impure helium environment[J]. Journal of Nuclear Science and Technology, 2023,60(8): 923-929.

[9] LI H, DU B, ZHENG W, et al. Study on corrosion behavior of two superalloys under two extreme atmospheres[J]. Annals of Nuclear Energy, 2023,181.

[10] WANG J, HAO Y, LI Y, et al. COMMISSIONING TEST STUDY ON RESIDUAL HEAT REMOVAL VENTILATION IN SPENT FUEL CANISTER UNLOADING STAGE OF HTR-PM PROJECT[C]//. International Conference on Nuclear Engineering, Proceedings, ICONE, 2023.

[11] ZHENG W, LI H, DU B, et al. INFLUENCE OF CO AND CO2 LEVELS IN IMPURE HELIUM ON THE HIGH TEMPERATURE CORROSION BEHAVIOR OF INCONEL 617[C]//. International Conference on Nuclear Engineering, Proceedings, ICONE, 2023.

[12] PENG L, ZHANG S, ZHANG H, et al. Study on tortuosity from 3D images of nuclear graphite grades IG-110 by Dijkstra's algorithm and fast marching algorithm[J]. Powder Technology, 2023,427.

[13] DU B, LI H, ZHENG W, et al. Study of oxidation behavior and tensile properties of candidate superalloys in the air ingress simulation scenario[J]. Nuclear Engineering and Technology, 2023,55(1): 71-79.

[14] HAO Y, LI Y, WANG J, et al. Structure-Performance-Cost Integration Multi-Objective Optimization Design for HTR Fuel Storage Canister[J]. Hedongli Gongcheng/Nuclear Power Engineering, 2023,44(2): 145-151.

[15] HAO Y, WANG J, LIN M, et al. Hybrid Surrogate Model-Based Multi-Objective Lightweight Optimization of Spherical Fuel Element Canister[J]. Energies, 2023,16(8).

[16] LI H, DU B, ZHENG W, et al. CORROSION STUDY OF INCONEL 617 ALLOY IN HTGR WITH IMPURE HELIUM ATMOSPHERE[C]//. International Conference on Nuclear Engineering, Proceedings, ICONE, 2023.

[17] DU B, CHENG H, LI H, et al. EFFECT OF METHANE IN HELIUM ON THE TENSILE PROPERTY OF SUPERALLOYS FOR VERY HIGH-TEMPERATURE REACTOR APPLICATIONS[C]//. International Conference on Nuclear Engineering, Proceedings, ICONE, 2023.

[17] ZHANG H, ZHANG L, XIAO H, et al. ESTIMATION OF IRRADIATION HISTORY OF FUEL SPHERES IN HTR-PM BASED ON GENETIC ALGORITHM[C]//. International Conference on Nuclear Engineering, Proceedings, ICONE, 2023.

[17] GONG M, WANG J, HAO Y, et al. CFD SIMULATION OF A SCALED MODEL OF THE STORAGE WELL IN SPENT FUEL DRY-STORAGE SYSTEM OF HTR-PM600[C]//. International Conference on Nuclear Engineering, Proceedings, ICONE, 2023.

[18] LI H, ZHENG W, DU B, et al. The high temperature corrosion of Incoloy 800H alloy at three different atmospheres[J]. Journal of Nuclear Science and Technology, 2023,60(2): 165-174.

[19] ZHENG W, ZHANG H, DU B, et al. Effect of impurity ratios on the high-temperature corrosion of Inconel 617 and Incoloy 800H in impure helium[J]. Annals of Nuclear Energy, 2023,189.

[20] LI H, ZHENG W, DU B, et al. Study on corrosion of T-22 alloy under high temperature condition of VHTR[J]. Journal of Nuclear Science and Technology, 2023,60(9): 1070-1078.

[21] LI H, ZHANG H, ZHENG W, et al. Study on oxidation kinetics of three kinds of candidate superalloys for VHTR under air ingress accident[J]. Annals of Nuclear Energy, 2023,189.

[22] HAO Y, WANG J, WU B, et al. Study on the most severe condition for structural assessment of nuclear fuel transport package under impact loading[J]. Progress in Nuclear Energy, 2022,153.

[23] DU B, YIN H, LI H, et al. Preliminary study on corrosion behavior and mechanical properties of inconel 617 in impure helium environment of vhtr[C]//. International Conference on Nuclear Engineering, Proceedings, ICONE, 2022.

[24] LI H, ZHENG W, YIN H, et al. Study on Decarburization and Oxidation Corrosion Behavior of T-22 Alloy in Impure Helium of High-temperature Gas-cooled Reactor[J]. Hedongli Gongcheng/Nuclear Power Engineering, 2022,43(4): 38-45.

[25] LI H, ZHENG W, DU B, et al. Effect of a cr2o3/-Al2o3 coating on the corrosion behavior of incoloy 800h alloy in high temperature impure helium[C]//. International Conference on Nuclear Engineering, Proceedings, ICONE, 2022.

[26] HAO Y, LI Y, WU B, et al. Optimization analysis of HTR-PM600 fresh fuel transport container under multiple impact loading conditions[J]. Annals of Nuclear Energy, 2022,175.

[27] WU B, WANG J, LI Y, et al. Design, Experiment, and Commissioning of the Spent Fuel Conveying and Loading System of HTR-PM[J]. Science and Technology of Nuclear Installations, 2022,2022.

[28] HAO Y, LI Y, LIN M, et al. Containment Integrity and Sealing Assessment for HTR-PM600 Fresh Fuel Transport Package Under Impact Loading[J]. Frontiers in Energy Research, 2022,10.

[29] ZHENG W, ZHANG H, DU B, et al. High-Temperature Corrosion Behavior of Incoloy 800H Alloy in the Impure Helium Environment[J]. Science and Technology of Nuclear Installations, 2022,2022.

[30] LI H, ZHENG W, YIN H, et al. Effect of Pre-oxidation on Corrosion Behavior of Three Kinds of Superalloys in Impure Helium of High-temperature Reactor[J]. Yuanzineng Kexue Jishu/Atomic Energy Science and Technology, 2022,56(6): 1069-1077.

[31] 李昊翔, 郑伟, 银华强, 等. T-22合金在高温气冷堆非纯氦气中脱碳和氧化腐蚀行为研究[J]. 核动力工程, 2022,43(04): 38-45.

[32] 李昊翔, 郑伟, 银华强, 等. 高温堆非纯氦气中预氧化对3种高温合金的腐蚀行为影响研究[J]. 原子能科学技术, 2022,56(06): 1069-1077.

[33] 郑伟, 李昊翔, 银华强, 等. 高温气冷堆非纯氦气环境下高温合金碳迁移的化学动力学研究[J]. 核动力工程, 2021,42(05): 226-231.

[34] LI J, WEI L, ZHENG Y, et al. Experimental study on the residual heat removal system in HTR-10[C]//. Journal of Physics: Conference Series, 2021.

[35] WANG F, WEI L, KANG T, et al. Experimental study on performance improvement of HTR-10 helium purification system[C]//. International Conference on Nuclear Engineering, Proceedings, ICONE, 2021.

[36] WANG F, CHEN X, XIE F, et al. Experimental design on performance improvement of the helium purification system of HTR-10[C]//. International Conference on Nuclear Engineering, Proceedings, ICONE, 2019.

[37] WEI L, DING D, LIU L, et al. Characteristic tests on transition core of HTR-10[C]//. International Conference on Nuclear Engineering, Proceedings, ICONE, 2018.

[38] WEI L, XIE F, CHEN X, et al. Summary and experience feedback on the restart and power operation After a long term shutdown of HTR-10[C]//. International Topical Meeting on High Temperature Reactor Technology, HTR 2016, 2016: 218-223.

[39]卢振明,陈晓彤,魏利强,等.HTR堆内碳素构件孔结构及吸湿特性研究[J].原子能科学技术,2016,50(03):477-483.

[40]魏利强,马涛,陈晓明,等.HTR-10数字化运行仪表与控制系统更新设计[J].原子能科学技术,2011,45(09):1093-1099.