Published Paper
[1] Zhang, ZH&; Sheng, XY*; Numerical study of smoothed particle Galerkin method in orthogonal cutting simulations, COMPUTATIONAL PARTICLE MECHANICS, 2025.4, 12(2), p933-945.
[2] Lanwen Wang；Sheng, XY*. Numerical Model Study on Rolling Contact Fatigue Damage of Bearing Steel. Chinese Congress of Computational Mechanics. 2023, (CCCM2023), August 20-23, 2023, Dalian.
[3]Lanwen Wang& ; Xuanyu Sheng*; Jianbin Luo. A peridynamic damage-cumulative model for rolling contact fatigue. Theoretical and Applied Fracture Mechanics, 2022.10, 121, p1-15.
[4] Lanwen Wang& ; Xuanyu Sheng*; Jianbin Luo. A peridynamic frictional contact model for contact fatigue crack initiation and propagation. Engineering Fracture Mechanics, 2022.4, 264, p1-17.
[5] Lanwen Wang& ; Xuanyu Sheng*; Jianbin Luo. Thermal-mechanical fully coupled analysis of high-speed angular contact ball bearings. Journal of Mechanical Science and Technology, 2021, 35(2), p669-678.
[6] Fluid-solid Coupling Analysis of the Pressure Expansion of Packers. Journal of Physics: Conference Series, April 2020, 1486(7), p1-8.
[7] Lanwen Wang&; Xuanyu Sheng*. Friction and wear performance of sliding bearing seat of reactor pressure vessel. Wear, March 2020, 444-445: p1-8.
[8] Lanwen Wang&; Xuanyu Sheng*; Jiayue Sheng. Analysis of the Pressure Expansion of Bridge Plug Tools and Packers by Equivalent Material Method. Journal of Physics: Conference Series, 2019，1187(3)，p1-7.
[9] Yibo Fan; Jianguang Li; Xuanyu Sheng*; Lanwen Wang&. Seismic Performance Analysis of Emergency Diesel Engine Retarder in Nuclear Power Plant. Journal of Physics: Conference Series, 2019，1314(1)，p1-8.
[10] Jianguang Li; Yibo, Fan; Xuanyu Sheng*; Lanwen Wang&. Disassembly simulation of main pipe insulation layer of nuclear power plant pressure vessel based on DELMIA. Journal of Physics: Conference Series, 2019，1303(1)，p12047-12052.
[11] Lanwen Wang&; Xuanyu Sheng*. Analysis of the stress condition and bearing capacity of the wellhead using the finite element method. Mechanical Research and Application, 2019, 32(2), p78-80.
[12] Lanwen Wang&; Xuanyu Sheng*.Analysis of the pressure expansion and structural optimization of packers. Mechanical Manufacturing, 2019, 57(9), p50-54.
[13] Lanwen Wang&; Xuanyu Sheng*. Motion simulation of a heavy vehicle boarding problem based on CATIA. Practical Automotive Technology, 2019, 4, pp. 95-97.
[14] Li Jianguang; Fan Yibo; Sheng, Xuanyu*; Wang Lanwen& . Simulation of Hoisting Bottom Pool of Nuclear Power Plant by Open-Top Construction Method. Advances in Intelligent Systems Research, 2019, 165, p46-50.
[15] Ye Kai; Zhang Yaoli*; Sheng Xuanyu; Li Ning; Yang Yinglin; Chen Yifen. Numerical analysis of the flow behavior in a helically coiled once through steam generator. Nuclear Engineering and Design, 2018, 330, p187-198.
[16] Peng Tianji; Zhou Zhiwei*; Xiao Sicong; Sheng Xuanyu; Gu Long. Thermal-hydraulic modeling and transient analysis of helium-cooled tungsten target coupled with ADS core. Annals of Nuclear Energy, 2016, 87, p612-620.
[17] Junwei Hao; Yaoli Zhang*; Jianxiang Zheng; Zhiwei Zhou; Xuanyu Sheng; Gang Hong; Kai Ye; Ning Li. Analysis of Density Wave Oscillations in Helically Coiled Tube Once-Through Steam Generator. Science and Technology of Nuclear Installations, 2016, v2016, p1-10.
[18] Li, H. D.; Sheng, X. Y.*; Zhang, W. D. Ergonomics Analysis of Hoisting Large Equipment Based on DELMIA. 4th international conference on materials engineering for advanced technologies (ICMEAT 2015), 2015, p31-35.
[19] Peng Tianji; Zhou Zhiwei*; Sheng Xuanyu; Gu Long. Concept design and thermal-hydraulic analysis for helium-cooled ADS. International Topical Meeting on Nuclear Reactor Thermal Hydraulics, 2015, 9, p7900-7912.
[20] S.C. Xiao, Jing Zhao*; X. Heng; X. Y. Sheng, Z. Zhou, Y. Yang. Burn up study of an innovative natural uranium-thorium fueled reprocessing free fusion-fission hybrid reactor blanket with closed thorium-uranium fuel cycle.Fusion Science and Technology, 2015, 68(3), p566-572.
[21] Zhang Hongzhi; Sheng Xuanyu. Simulation and stress analysis of U-shaped seam welding process based on ABAQUS. Advanced Materials Research, 2014, 900, p612-616.
[22] Sheng Xuanyu, Zhou Zhiwei. Isostatically Pressed Lithium Titanate and Lithium Zirconate Ceramic Spheres. The 1st Nuclear Fusion Materials Forum, Hefei, Anhui, May 12-15, 2014.
[23] Zhang Hongzhi; Sheng Xuanyu*. Dynamics simulation of large tower structure lifting process based on CABLE modeling. Applied Mechanics and Materials, 2014, 533, p145-153.
[24] Sheng Xuanyu* et.al. Strength analysis of high-pressure sulfur-resistant separators in gas fields. Mechanical design.2014, 31, p134-138.
[25]Bai Yongchao, Sheng Xuanyu*. Finite element analysis and simulation of penetration depth of perforating projectiles used in oil fields. Petroleum machinery.2013, 41(10), p33-36.
[26]Liu Sheng; Sheng Xuanyu*; Shang Yitong. Modification design by replacing perforated shells barrel based with 406 steel based on finite element analysis. Advanced Materials Research, 2013, 634-638(1), p3622-3627.
[27] Liu Sheng; Sheng Xuanyu* Theoretical analysis on the tribological properties of HTGR-10. Applied Mechanics and Materials, 2013, 278-280, p518-522.
[28] Liu Sheng; Sheng Xuanyu*, Kang Fangliang. Temperature Field Analysis of Concrete in Steam Generator Compartment of High-Temperature Gas-Cooled Reactor. Nuclear Power Engineering. 2010, 31(1), p49-56.
[29] Liu Sheng; Sheng Xuanyu*. Strength Analysis of Automobile Engines Based on Automatic Structured Mesh Generation. Computer Engineering and Design.2010, 31(10), p2316-2319.
[30] Sheng Xuanyu*, Wang Liankui. Reverse engineering of MIMICS-based components with internal cavities. (Science & Technology Review)2009, 7（27），p85-87.
[31] Liu Sheng; Sheng Xuanyu*. Performance analysis of O-rings used for sealing between stainless steel and aluminum alloy materials. (Atomic Energy Science and Technology)2009, 43(2), p157-161.
[32] Sheng Xuanyu*, Wang Liankui. Motion simulation of an aircraft landing gear retraction system. Computer Engineering and Design.2009, 30 (18)，p4245-4250.
[33]Kang Fangliang, Sheng Xuanyu*. Load estimation for casing repair in multi-expansion-head natural gas wells. Electromechanical Engineering Technology.2009, 38（07）, p56-58.
[34]Zhou Dan, Sheng Xuanyu*. Finite element contact analysis of horizontal channel "O" ring seal structure. Nuclear Power Engineering.2008, 29(5): p22-24.
[35] Sheng Xuanyu*. Wang Liankui. Temperature Field Analysis of Biological Shielding Layer in High-Temperature Gas-Cooled Reactor. Science & Technology Review. 2008, 26(13), p29-33.
[36] Sheng Xuanyu*, Sheng Xuanjun. A Preliminary Study on Human-Machine Engineering Simulation in Surgical Repair of Skull Defects. Science & Technology Review.2008, 26(18), p54-57.
[37]Chang Xiuqin, Sheng Xuanyu*,Kang Fangliang. Finite element analysis of a 3000m³ propane spherical tank. Petroleum engineering construction.2008, 8，p21-24.
[38] Sheng Xuanyu*,zhang Hongzhi. Strength verification of a 150,000 m³ crude oil storage tank based on ABAQUS finite element analysis. (Petroleum Engineering Construction)，2008, 34（1），p17-20.
[39] Liu Sheng; Sheng Xuanyu*. Design and Strength Analysis of Cold Neutron Channel Square Tube. (Mechatronics Engineering Technology)，2007, 36（10），p78-80.
[40] Sheng Xuanyu*. Wang Liankui. Strength Analysis of High-Speed Rotary Couplings. Science & Technology Review, 2007, 25(23), pp. 42-44.
[41] Liu Sheng; Sheng Xuanyu*. Finite element analysis of rubber seals for oil well casing. Science & Technology Review, 2007, 25(14), pp. 49-52.
[42] Sheng Xuanyu*,zhang Hongzhi. Optimization Design of a 150,000 m³ Crude Oil Storage Tank. Science & Technology Review, 2007, 25(11), pp. 39-44.
[43] Sheng Xuanyu*,Zhu shutang, et al. Research on vertical high-speed gearbox in high-temperature gas-cooled reactor helium turbine cycle power generation system. Science & Technology Review, 2007, 25(8), p30-33.
[44] Sheng Xuanyu*. Analysis of the Influence of Humidity on Static Friction Coefficient Based on Fractal Contact. Journal of Heze University, 2006, 28(5), pp. 32-35.
[45] Sheng Xuanyu*. Seismic analysis of the reactor water purification system of a hospital neutron irradiator. Nuclear Science and Engineering, 2006, 26(4), pp. 327-331.
[46] Sheng XuanYu*; D. Zhou&; S.Y. Yu; X.X. Wu. Modification of rotary gate of horizontal neutron channel. Nuclear Engineering and Design, 2006, 236(22), p2343-2347.
[47] Xiaowei Luo; Suyuan Yu*; Xuanyu Sheng; Shuyan He. The influence of roughness on tribological properties of nuclear grade graphite. Journal of Nuclear Materials, 2006, 350(1), p74-82.
[48] Sheng XuanYu*. Solid modeling and seismic calculation of auxiliary pumps for reactors. Science & Technology Review, 2006, 24(07), pp. 51-53.
[49] Sheng XuanYu*. Three-dimensional solid model calculation of seismic strength of reactor main pump. Nuclear Power Engineering, 2005, 26(5), p472-474.
[50] Sheng XuanYu*.Zhou Dan, Liu Sheng. Study on anti-sliding wear properties of CuNiCoBe material. Mechanical Science and Technology, 2005, 24(11), p1265-1267.
[51] Luo Xiaowei; Yu Suyuan*; Sheng Xuanyu; He Shuyan. Wear performance of IG-11 graphite in different atmospheres. Journal of Tribology, 2005, 25(2), p173-177.
[52] Luo Xiaowei; Yu Suyuan*; Sheng Xuanyu; He Shuyan. Temperature effect on IG-11 graphite wear performance. Nuclear Engineering and Design, 2005, 235(21) p2261-2274.
[53] Sheng Xuanyu; Zhou Dan, Wu xiaosheng et al. Simulated wear of moving parts of lifting plate valve in lock. Lubrication and Sealing, 2005, 5, pp. 66-69.
[54] Luo Xiaowei; Yu Suyuan*; Sheng Xuanyu; He Shuyan. Effect of temperature on the tribological properties of graphite used in a 10MW high-temperature gas-cooled reactor. Journal of Tribology, 2004, 24(5), pp. 402-405.
[55] Sheng Xuanyu; Shi Yongchang, He Shuyan. Improved design of sealing structure for cold neutron channels. The 13th National Conference on Reactor Structural Mechanics, Shanghai, August 2004.
[56] Luo Xiaowei; Yu Suyuan*; Sheng Xuanyu; He Shuyan. Study on the tribological properties of graphite for high-temperature gas-cooled reactors. Atomic Energy Science and Technology, 2004, 38(3), p226-230.
[57] Sheng Xuanyu*, Yu Suyuan. Performance in Resistance to Surface Fatigue for Cr3C2–25%NiCr Coatings by Plasma Spray and CDS Spray. Tribology Letters. 2004, 16(3), p173-180.
[58] X. Sheng*; S. Yu ; X. Luo; S. He. Wear behavior of graphite studies in an air-conditioned environment. Nuclear Engineering and Design, 2003, 223(2), p109-115.
[59] Zhang Jige, Wu Yuanqiang, Sheng Xuanyu*. Experimental study on dynamic characteristics of a novel electromagnetic drive mechanism for control rods. Nuclear Science and Engineering, 2003, 23(2), pp. 123-126.
[60] Sheng Xuanyu*, Yu Suyuan. Distribution patterns and fractal contours of graphite wear particles in high-temperature gas-cooled reactors. Nuclear Power Engineering, September 2002, Special Issue, pp. 335-337.
[61]Lv Xuefeng, Sheng Xuanyu, Yu Suyuan. A Two-Parameter Model for the Behavior of Graphite Particles in Reactors. Nuclear Power Engineering, September 2002, Special Issue, pp. 328-330.
[62] Sheng Xuanyu, Yu Suyuan. Friction coefficient of reactor graphite considering changes in elastic modulus. Nuclear Power Engineering, September 2002, Special Issue, pp. 322-3324.
[63]Zhang Jige, Wu Yuanqiang, Zhang Zhengming, Sheng Xuanyu, Experimental Study on Static Characteristics of a Novel Electromagnetic Drive Mechanism for Control Rods. Nuclear Power Engineering, September 2002, Special Issue, pp. 231-233.
[64]Wu Yuanqiang, Wang Jiachun, Zhang Jige, Sheng Xuanyu, Et al. Impact Test Study on Hydraulically Driven Control Rod Model. Nuclear Power Engineering, September 2002, Special Issue, pp. 132-133.
[65]Shi YongChang, Sheng Xuanyu, Instability and Deformation of Long Metal Rods under Temperature Effects. Nuclear Power Engineering, September 2002, Special Issue, pp. 77-79.
[66]Yu Suyuan, Lv Xuefeng, Sheng Xuanyu, Hua Hongliang. Simulation of particle distribution in free molecular regions using a dual-parameter discrete partitioning model. Journal of Process Engineering, 2002, 2, pp. 65-69.
[67]Wu Yuanqiang, Sheng Xuanyu, Wang Fuxing， Chen Jianmin. Solid lubrication technology for high-temperature gas-cooled reactors under helium atmosphere. Nuclear Power Engineering, 2001, 22 (5), pp. 460-464
[68] Sheng Xuanyu, Yu Suyuan. Analysis of the friction surface morphology of domestically produced graphite for reactors. Nuclear Power Engineering, 2001, 22 (5), p401-405.
[69] Sheng Xuanyu, Yu Suyuan. Research on the tribological properties of graphite materials in high-temperature gas-cooled reactors. Nuclear Power Engineering, 2001, 22 (4), pp. 318-320.
[70] Luo XiaoWei; Yu SuYuan*; Sheng, XuanYu; He SuYan. Graphite friction coefficient for various conditions. Science in China （Series a）mathematics physics astronomy, 2001, 44, 248-252
[71] Luo XiaoWei; Yu SuYuan*; Sheng, XuanYu; He SuYan. Comparison of the frictional properties of graphite for three types of reactors. High Technology Communications, 2001, 05, pp. 97-101.
[72] Sheng, XuanYu, Luo Jinbin, Wen Shizhu. Influence of relative humidity on the static friction coefficient of several friction pairs. Journal of Tribology, 2001, 21(1), p42-46.
[73] Sheng, XuanYu, Luo Jinbin, Wen Shizhu. Preparation of inlaid self-lubricating spherical plain bearings and their lubricating materials. Mechanical Design, 2000, 8, pp. 44-46.
[74] Luo Jinbin, Wen Shizhu, Huang Ping, Sheng, XuanYu, Aging characteristics of lubricating films. Journal of Tsinghua University, 1999, 39(2), p1-5.
[75] Sheng, XuanYu, A Novel Method to Increase the Dissolution Rate of Crude Salt. China Chlor-Alkali, 1999, 4, pp. 31-32
[76] Sheng, XuanYu, Wang Jianmin. Study on wear resistance of three types of copper-based lock components. Journal of Hydraulic and Waterway Engineering, 1999, 12, pp. 348-354.
[77] Sheng, XuanYu, Luo Jinbin, Wen Shizhu. Static friction coefficient of graphite-metal friction pairs. Lubrication and Sealing, 1999, 3, pp. 11-13.
[78] Sheng, XuanYu, Luo Jinbin, Wen Shizhu. Wear resistance of lock materials under lubrication conditions. Journal of Tsinghua University, 1998, 38(4), pp. 47-51.
[79] Sheng, XuanYu, Luo Jinbin, Wen Shizhu. Prediction of Static Friction Coefficient Based on Fractal Contact. Chinese Journal of Mechanical Engineering, 1998, 9(7), p16-18.
Published textbooks and monographs
[1] Sheng, XuanYu. ADINA Finite Element Analysis Example Tutorial, Chongqing University Press, 2019
[2] Sheng, XuanYu. CATIA Tolerance Design and Real-Time Rendering Tutorial, Machinery Industry Press, 2016.
[3] Sheng, XuanYu. CATIA Machining Technology Tutorial, Machinery Industry Press, 2016.
[4] Sheng, XuanYu. CATIA Motion Analysis Tutorial, Machinery Industry Press, 2015.
[5] Sheng, XuanYu. CATIA Visual Design Tutorial, Machinery Industry Press, 2015.
[6] Sheng, XuanYu. CATIA Nonlinear Finite Element Analysis Tutorial, Machinery Industry Press.
[7] Sheng, XuanYu. CATIA V5 R20 Basic Introductory Tutorial, Science Press, 2011.
[8] Sheng, XuanYu. CATIA V5 Fundamentals and Examples Tutorial, Chemical Industry Press, 2009.
[9] Sheng, XuanYu. ABAQUS FOR CATIA Finite Element Analysis Tutorial, Machinery Industry Press, 2009.
[10] Sheng, XuanYu. DELMIA Human Factors Simulation Tutorial, Machinery Industry Press, 2009.
[11] Sheng, XuanYu. CATIA Sheet Metal Design Tutorial, Machinery Industry Press, 2009.
[12] Sheng, XuanYu. CATIA Finite Element Analysis Tutorial, Machinery Industry Press, 2009.
[13] Sheng, XuanYu. CATIA Mechanical Design Commands Explained, Machinery Industry Press, 2009
[14] Sheng, XuanYu. CATIA Sheet Metal Design Tutorial, Chemical Industry Press, 2008
[15] Sheng, XuanYu. CATIA V5 Kinematics and Mechanics Analysis Tutorial, Chemical Industry Press, 2008
[16] Sheng, XuanYu. CATIA Welding Design Examples Tutorial, Machinery Industry Press, 2005
[17] Sheng, XuanYu. CATIA Mechanical Design Commands Explained, Harbin Institute of Technology Press, 2005
[18] Sheng, XuanYu. CATIA Typical Mechanical Part Design Examples Tutorial, Machinery Industry Press, 2005
[19] Sheng, XuanYu. CATIA Finite Element Analysis Commands Explained and Examples, Machinery Industry Press, 2005
[20] Sheng, XuanYu. CATIA Curves and Surfaces Functions Explained, Machinery Industry Press, 2004
[21] Sheng, XuanYu. CATIA V5R10 Mechanical Design Example Tutorial, Peking University Press, 2003
[22] Sheng, XuanYu. CATIA 3D Mechanical Design Examples, Machinery Industry Press, 2003
[23] Sheng, XuanYu. CATIA 3D Modeling: Introduction and Advanced, Machinery Industry Press, 2003
Authorized Invention Patent
1. A crane device for a central storage tank for spent fuel . ZL201811252659.0, 2024.09.03
2. A spent fuel storage pool . ZL201811592699.X, 2024.06.25
3. A ceramic nano-coated nuclear fuel cladding. ZL201711166673.4 2024.05.28
4. Main pipeline installation and adjustment device. ZL201810457574.X 2024.03.08
5. A liquid windowless spallation structure using a liquid target as a coolant. ZL201710641446.6 2023.12.08
6. A self-pressurized integrated cold container reactor. ZL201710641302.0 2023.10.27
7. A preparation system and method for medical radiation protection equipment. ZL201710081845.1 2023.08.22
8. For integrated pressure differential-based passive shutdown systems and nuclear reactors. ZL201710642371.3 2023.08.22
9. An accelerator-driven subcritical gas-cooled reactor. ZL201710428993.6 2023.08.01
10. Integrated pressurized water reactor. ZL201710642496.6 2023.05.23
11. A refueling system for an integrated stack. ZL201710429439.X 2023.05.23
12. A core structure of an integrated reactor and a nuclear reactor. ZL201710639876.4 2023.05.23
13. A steam generator and nuclear equipment suitable for lead-bismuth reactors. ZL201810290358.0 2019.10.29
14. A test device for a pool-type liquid heavy metal cooled reactor steam generator. ZL201810288506.5 2019.10.15
15. A self-locking jaw clutch device for shaft end connection. ZL201610999872.2 2019.5.21
16. A material changing device with friction reduction and self-locking function. ZL201610999873.7 2019.3.8
17. A containment air-cooling device and nuclear facility. ZL201710048064.2 2018.12.25
18. A pressure vessel for a lead-bismuth fast reactor. ZL201611260492.3 2018.11.20
19. A reactor top reflector replacement device. ZL201710079169.X 2018.11.20
20. An ADS containment system. ZL201710044478.8 2018.11.13
21. A graphite replacement device on the outside of a gas-cooled reactor. ZL201611265415.7 2018.10.16
22. A replacement device for the central graphite column of a nuclear reactor. ZL201611179172.5 2018.09.21
23. A reactor graphite brick grasping mechanism. ZL201611260434.0 2018.09.21
24. An ADS spallation target and nuclear facility. ZL201710081578.8 2018.9.21
25. An ADS integrated reactor top structure and nuclear power generation equipment. ZL201710051784.4 2018.8.14
26. A heavy oil thermal recovery process and its dedicated equipment. CN201410413071.4 2018.06.01.
27. A self-balancing fuel assembly gripping mechanism. ZL201610999850.6 2018.5.18
28. A fuel assembly gripping linkage device. ZL201611000763.1 2018.05.08
29. A fuel assembly gripping device. ZL201611000285.4 2018.01.02
30. An overload protection rotating mechanism for reactor refueling equipment. ZL201611007279.1 2017.12.19.
31. A core structure of a lead-bismuth stack ADS. ZL201610999874.1 2017.12.19
32. A drive system for a fuel assembly gripping device. ZL201611001372.1 2017.11.10
33. Grabbing device for fuel assembly. CN:201611000285:A 2017.02.15
34. Self-balancing fuel assembly grabbing mechanism. CN:201610999850:A. 2017.02.22
35. Overload preventing rotating mechanism for reactor refueling equipment. CN:201611007279:A. 2017.02.22
36. Driving system of fuel assembly gripping apparatus. CN:201611001372:A 2017.02.15
37. Reactor core structure of lead-bismuth reactor ADS. CN:201610999874:A 2017.02.01
38. Capturing linking device for fuel component. N:201611000763:A 2017.01.11
39. A boltless sealing structure. CN201620803766.8 2017.01.04
40. Solid spallation target for accelerator-driven subcritical nuclear energy systems. CN201310186564.4 2016.12.28
41. Hybrid reactor system and operation method utilizing cross-arranged water-cooled thorium-uranium fuel modules. CN201410093281.X 2016.07.13
42. A Th-U self-sustaining cycle fully molten salt fuel hybrid reactor system and its operation method. ZL201410093302.8 2016.06.29
43. Heavy oil thermal recovery process and special device thereof. CN:201410413071:A 2015.02.04
44. A lithium zirconate ceramic sphere tritium breeding material and its preparation method. ZL201310134204.X 2014.11.26
45. Hybrid reactor system arranged by means of water-cooling thorium fuel modules and water-cooling uranium fuel modules in staggered mode and operating method. CN:201410093281:A 2014.06.25
46. Th-U self-sustaining circulating full fused salt fuel hybrid reactor system and operation method thereof. CN:201410093302:A 2014.06.25
47. Solid spallation target for ADS (Accelerator Driven Sub-critical System). CN:201310186564:A 2013.09.18
48. Vertical high-speed gear reducer. ZL200510011655.X 2007.12.19
49. Gas dynamic sealing device for direct circulation in high-temperature gas-cooled reactors. ZL200510011235.1 2007.04.25
50. Damperless support system for the pressure vessel of a modular high-temperature gas-cooled reactor. ZL200510011121.7
51. Shaftless rotary gate for shielding nuclear reactor experimental channels. ZL200410098951.3 2007.03.07
52. A hot gas duct that prevents convection and depressurization. ZL200410009946.0 2006.11.01
53. Dynamic sealing device for vertical shaft structure. CN200520114521.6 2006.09.20
54. A hot gas duct pressure shell connection structure. ZL200410009876.9 2006.08.30
55. A sealing structure for aluminum alloy and stainless steel flanges. ZL200410009945.6 2006.08.30
56. A sealing structure for an aluminum alloy flange. ZL200410098950.9 2006.08.02
57. A long-distance gravity automatic grasping and releasing mechanism. CN03100289.7 2004.12.29.
58. Multi-axis rotary gate for experimental nuclear reactor. CN00124425.6 2003.11.05
Research projects
1) Research on Multi-stage Assessment Method for Fatigue Life of Rotary Guide Key Structures. 2024.10.21-2025.06.30.
2) Aircraft assembly digital simulation based on DELMIA. 2024.03.26-2024.12.31
3) Digital Prototype Simulation Verification of Underwater Platform. 2024.01.12-2025.10.30
4) Preparation of super-lubricating module coating. 2023.09.26-2025.12.31
5) Contract for the Development of Radioactivity Measurement Equipment for HIC Waste Packages. 2023.06-2024.03
6) Contract for the Development of Radioactivity Measurement Equipment for HIC Waste Packages. 2022.12-2023.12
7) Solenoid valve O-ring failure root cause analysis service contract. 2022.04.01-2022.06.30
8) Research on high-speed rotor system supported by electromagnetic bearing. 2022.01-2024.12
9) Full-coverage linear module friction analysis technical service. 2021.12.23-2022.12.31
10) Technical services for friction analysis of moving equipment. 2021.12.17-2022.12.31
11) Demonstration Fast Reactor Container and In-core Components Three-Dimensional Thermal-Fluid Transient Calculation Verification R&D Contract. 2021.03-2022.04
12) Study on the simulation prediction model of fretting damage and wear mechanism of heat transfer tubes in steam generator. 2020.12.03-2022.03.31
13) Safety bar drive mechanism computational simulation and structural optimization technical service contract. 2020.11.2-2020.12.1
14) 3D lightweighting and BIM visualization of the HEPS project. 2020.10.13-2021.11.12
15) Rendering of the friction test bench. 2020.09.01-2021.06.30
16) Strength calculation of the control rod drive mechanism for the equipment missing items project. 2020.07.11-2020.08.30
17) Development of rapid reconstruction technology for insurance scenarios based on SLAM technology. 2020.06.01-2020.12.30
18) Simulation Verification of Enclosed Busbar for 1750MW Nuclear Power Plant. 2020.04.10-2021.05.31
19) Optimized Design and Development of 20t Multi-Specification Aluminum Plate Lifting Tool. 2019.11.01-2020.12.31
20) Equipment Cost: Tester for Structural Tribology and Structural Integrity in High-Radioactive Underwater Environments. 2019.12-2022.11
21) Decay Mechanism and Design Method of Dynamic and Static Stiffness, Accuracy, and Thermal Characteristics of Bearings. 2019.07-2022.06
22) Procurement of Data for Overseas Cavern Disposal Sites for the TYR Project. 2019.4-2019.12.31
23) Prototype and bench design and testing of sliding plate support structure for offshore nuclear power platforms. 2019.04.02-2020.12.31
24) Construction of dynamic simulation system for pilot workshop. 2018.08-2019.06
25) Procurement of prototype and testing of sliding plate support structure. 2018.09-2019.07
26) Development of prototype lead-bismuth fast reactor fuel assembly. 2018.8.30-2018.10.31
27) Stress analysis of high sulfur-resistant, high expansion rate bridge plug and packer. 2018.04.25-2018.08.31
28) Tribological Wear Behavior of SIMP Steel Friction Pairs in Liquid Lead-Bismuth. 2018.01.01-2019.12.31
29) High-Resolution, High-Security Real-Time Image Transmission System for Enhancing Soldier Capabilities. 2017.07.01-2018.06.30
30) Development of Fabrication and Welding Technology for OTSG Heat Transfer Tubes. 2016.09-2017.06
31) Development of High-Gain Cladding Structure and Thermal Design and Experimental Module. 2015.10-2019.08.31
32) ACPR50S Small Reactor Direct Current Steam Generator (OTSG) Scheme Design. 2015.05-2018.12
33) Technical Support for 3D Collaborative Design in Small Reactor R&D. 2015.01-2016.05
34) System Integration Research of a Novel ADS Target Reactor Based on Particle Flow. 2015.01-2018.12
35) 3OTSG Thermal-Hydraulic Model Construction and Experimental Requirements Analysis Technical Service Contract. 2014.07.07-2014.09.07
36) Research on Helium-Cold Blanket Core and Engineering Thermophysics Technology for Fusion Reactors. 2011.11-2014.12.
37) Procurement Contract for Lightweight Testing of 3D Models for Nuclear Power Plants. 2018.09-2019.07
