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1

Miniaturization of CMOS

Radamson, Henry H., He, Xiaobin, Zhang, Qingzhu, Liu, Jinbiao, Cui, Hushan, Xiang, Jinjuan, Kong, Zhenzhen, Xiong, Wenjuan, Li, Junjie, Gao, Jianfeng, Yang, Hong, Gu, Shihai, Zhao, Xuewei, Du, Yong, Y

Journal:

Year:

2019

Language:

english

File:

PDF, 14.36 MB

english, 2019

2

Experimental investigation on the Leidenfrost phenomenon of droplet impact on heated silicon carbide surfaces

Wang, ZeFeng, Xiong, Jinbiao, Yao, Weiyi, Qu, Wenhai, Yang, Yanhua

Journal:

International Journal of Heat and Mass Transfer

Year:

2019

Language:

english

File:

PDF, 4.22 MB

english, 2019

3

State of the Art and Future Perspectives in Advanced CMOS Technology

Radamson, Henry H., Zhu, Huilong, Wu, Zhenhua, He, Xiaobin, Lin, Hongxiao, Liu, Jinbiao, Xiang, Jinjuan, Kong, Zhenzhen, Xiong, Wenjuan, Li, Junjie, Cui, Hushan, Gao, Jianfeng, Yang, Hong, Du, Yong, X

Journal:

Year:

2020

File:

PDF, 27.29 MB

2020

4

Turbulence modeling for mass transfer enhancement by separation and reattachment with two-equation eddy-viscosity models

Jinbiao Xiong, Seiichi Koshizuka, Mikio Sakai

Journal:

Nuclear Engineering and Design

Year:

2011

Language:

english

File:

PDF, 1.33 MB

english, 2011

5

Evaluation Methods for Corrosion Damage of Components in Cooling Systems of Nuclear Power Plants by Coupling Analysis of Corrosion and Flow Dynamics (V) Flow-Accelerated Corrosion under Single- and Two-phase Flow Conditions

OKADA, Hidetoshi, UCHIDA, Shunsuke, NAITOH, Masanori, XIONG, Jinbiao, KOSHIZUKA, Seiichi

Journal:

Journal of Nuclear Science and Technology

Year:

2011

Language:

english

File:

PDF, 883 KB

english, 2011

6

Numerical investigation on mass transfer enhancement downstream of an orifice

Xiong, Jinbiao, Cheng, Xu, Yang, Yanhua

Journal:

International Journal of Heat and Mass Transfer

Year:

2014

Language:

english

File:

PDF, 2.05 MB

english, 2014

7

A hybrid acceleration method to pin-by-pin calculations using the heterogeneous variational nodal method

Zhang, Tengfei, Xiong, Jinbiao

Journal:

Annals of Nuclear Energy

Year:

2019

Language:

english

File:

PDF, 2.03 MB

english, 2019

8

Conceptual design of an innovative reduced moderation thorium‐fueled small modular reactor with heavy‐water coolant

Zhang, Tengfei, Xiong, Jinbiao, Liu, Xiaojing, Chai, Xiang, Li, Wei, Cheng, Xu

Journal:

International Journal of Energy Research

Year:

2019

Language:

english

File:

PDF, 2.79 MB

english, 2019

9

Experimental and analytical study on heat dissipation mechanisms during spent fuel unloading in sodium fast reactor

Xiong, Jinbiao, Wu, Zenghui, Chen, Xiang, Zhang, Tengfei

Journal:

Annals of Nuclear Energy

Year:

2020

Language:

english

File:

PDF, 2.84 MB

english, 2020

10

Experimental investigation on split-mixing-vane forced mixing in pressurized water reactor fuel assembly

Xiong, Jinbiao, Qu, Wenhai, Zhang, Tengfei, Chai, Xiang, Liu, Xiaojing, Yang, Yanhua

Journal:

Annals of Nuclear Energy

Year:

2020

Language:

english

File:

PDF, 4.94 MB

english, 2020

11

Numerical simulation of turbulent natural convection in an enclosure with a curved surface heated from below

Chai, Xiang, Li, Wei, Chen, Bin, Liu, Xiaojing, Xiong, Jinbiao, Cheng, Xu

Journal:

Progress in Nuclear Energy

Year:

2020

File:

PDF, 1.64 MB

2020

12

Experimental investigation on the transient film boiling heat transfer during quenching of FeCrAl

Wang, Zefeng, Zhong, Mingjun, Deng, Jian, Liu, Yu, Huang, Huijian, Zhang, Yong, Xiong, Jinbiao

Journal:

Annals of Nuclear Energy

Year:

2021

File:

PDF, 3.94 MB

2021

13

Investigation on droplet impingement erosion during steam generator tube failure accident

Jinbiao Xiong, Seiichi Koshizuka, Mikio Sakai, Hiroyuki Ohshima

Journal:

Nuclear Engineering and Design

Year:

2012

Language:

english

File:

PDF, 856 KB

english, 2012

14

Lagrangian–Lagrangian modeling for a solid–liquid flow in a cylindrical tank

Mikio Sakai, Yusuke Shigeto, Xiaosong Sun, Takuya Aoki, Takumi Saito, Jinbiao Xiong, Seiichi Koshizuka

Journal:

Chemical Engineering Journal

Year:

2012

Language:

english

File:

PDF, 1.58 MB

english, 2012

15

Investigation of Droplet Impingement onto Wet Walls Based on Simulation Using Particle Method

XIONG, Jinbiao, KOSHIZUKA, Seiichi, SAKAI, Mikio

Journal:

Journal of Nuclear Science and Technology

Year:

2011

Language:

english

File:

PDF, 1.95 MB

english, 2011

16

Turbulence modelling for supercritical pressure heat transfer in upward tube flow

Xiong, Jinbiao, Cheng, Xu

Journal:

Nuclear Engineering and Design

Year:

2014

Language:

english

File:

PDF, 2.00 MB

english, 2014

17

Laser Doppler measurement and CFD validation in 3×3 bundle flow

Xiong, Jinbiao, Yu, Yang, Yu, Nan, Fu, Xiaoliang, Wang, Hongyan, Cheng, Xu, Yang, Yanhua

Journal:

Nuclear Engineering and Design

Year:

2014

Language:

english

File:

PDF, 2.50 MB

english, 2014

18

Numerical analysis on supercritical water heat transfer in a 2×2 rod bundle

Xiong, Jinbiao, Cheng, Xu, Yang, Yanhua

Journal:

Annals of Nuclear Energy

Year:

2015

Language:

english

File:

PDF, 3.68 MB

english, 2015

19

CFD Application to Hydrogen Risk Analysis and PAR Qualification

Xiong, Jinbiao, Yang, Yanhua, Cheng, Xu

Journal:

Science and Technology of Nuclear Installations

Year:

2009

Language:

english

File:

PDF, 2.51 MB

english, 2009

20

Experimental investigation on anisotropic turbulent flow in a 6×6 rod bundle with LDV

Xiong, Jinbiao, Yu, Nan, Yu, Yang, Fu, Xiaoliang, Cheng, Xu, Yang, Yanhua

Journal:

Nuclear Engineering and Design

Year:

2014

Language:

english

File:

PDF, 4.33 MB

english, 2014

21

[ASME 2012 20th International Conference on Nuclear Engineering and the ASME 2012 Power Conference - Anaheim, California, USA (Monday 30 July 2012)] Volume 4: Codes, Standards, Licensing, and Regulatory Issues; Fuel Cycle, Radioactive Waste Management and Decommissioning; Computational Fluid Dynamics (CFD) and Coupled Codes; Instrumentation and Co - CFD Modeling of Mass Transfer in the Flow Through an Orifice With ζ- f Model

Xiong, Jinbiao, Cheng, Xu, Yang, Yanhua

Year:

2012

Language:

english

File:

PDF, 1.44 MB

english, 2012

22

Numerical Analysis of Droplet Impingement Using the Moving Particle Semi-implicit Method

XIONG, Jinbiao, KOSHIZUKA, Seiichi, SAKAI, Mikio

Journal:

Journal of Nuclear Science and Technology

Year:

2010

Language:

english

File:

PDF, 1.90 MB

english, 2010

23

Numerical investigation of bubble wake properties in the moving liquid with LES model

Chai, Xiang, Liu, Xiaojing, Xiong, Jinbiao, Cheng, Xu

Journal:

Journal of Nuclear Science and Technology

Year:

2016

Language:

english

File:

PDF, 1.28 MB

english, 2016

24

[Society of Petroleum Engineers SPE Europec featured at 78th EAGE Conference and Exhibition - Vienna, Austria (2016-05-30)] SPE Europec featured at 78th EAGE Conference and Exhibition - A New Non-Darcy Flow Model for Low Velocity Multiphase Flow in Tight Reservoirs

Xiong, Yi, Yu, Jinbiao, Sun, Hongxia, Yuan, Jiangru, Huang, Zhaoqin, Wu, Yu-shu

Language:

english

File:

PDF, 1.40 MB

english

25

A New Non-Darcy Flow Model for Low-Velocity Multiphase Flow in Tight Reservoirs

Xiong, Yi, Yu, Jinbiao, Sun, Hongxia, Yuan, Jiangru, Huang, Zhaoqin, Wu, Yu-shu

Journal:

Transport in Porous Media

Year:

2017

Language:

english

File:

PDF, 1.92 MB

english, 2017

26

[ASME 2014 22nd International Conference on Nuclear Engineering - Prague, Czech Republic (Monday 7 July 2014)] Volume 4: Radiation Protection and Nuclear Technology Applications; Fuel Cycle, Radioactive Waste Management and Decommissioning; Computational Fluid Dynamics (CFD) and Coupled Codes; Reactor Physics and Transport Theory - Numerical Simulation of Thermal Behavior of a Molten Droplet Covered With Vapor Film

Zhong, Mingjun, Lin, Meng, Xiong, Jinbiao, Li, Yankai, Yang, Yanhua

Year:

2014

Language:

english

File:

PDF, 490 KB

english, 2014

27

Coupling of neutronics and thermal-hydraulics codes for the simulation of reactivity insertion accident for LFR

Yang, Dongmei, Liu, Xiaojing, Xiong, Jinbiao, Chai, Xiang, Cheng, Xu

Journal:

Progress in Nuclear Energy

Year:

2018

Language:

english

File:

PDF, 885 KB

english, 2018

28

PIV measurement of cross flow in a rod bundle assisted by telecentric optics and matched index of refraction

Xiong, Jinbiao, Qu, Wenhai, Wu, Zenghui, Cheng, Xu

Journal:

Annals of Nuclear Energy

Year:

2018

Language:

english

File:

PDF, 2.65 MB

english, 2018

29

CFD simulation of swirling flow induced by twist vanes in a rod bundle

Xiong, Jinbiao, Cheng, Ruiqi, Lu, Chuan, Chai, Xiang, Liu, Xiaojing, Cheng, Xu

Journal:

Nuclear Engineering and Design

Year:

2018

Language:

english

File:

PDF, 3.63 MB

english, 2018

30

High-fidelity PIV measurement of cross flow in 5 × 5 rod bundle with mixing vane grids

Qu, Wenhai, Xiong, Jinbiao, Chen, Shilong, Cheng, Xu

Journal:

Nuclear Engineering and Design

Year:

2019

File:

PDF, 15.55 MB

2019

31

Growth of SiGe layers in source and drain regions for 10 nm node complementary metal-oxide semiconductor (CMOS)

Wang, Guilei, Kolahdouz, M., Luo, Jun, Qin, Changliang, Gu, Shihai, Kong, Zhenzhen, Yin, Xiaogen, Xiong, Wenjuan, Zhao, Xuewei, Liu, Jinbiao, Yang, Tao, Li, Junfeng, Yin, Huaxiang, Zhu, Huilong, Wang,

Journal:

Journal of Materials Science: Materials in Electronics

Year:

2019

Language:

english

File:

PDF, 2.27 MB

english, 2019

32

Predictions of quench temperature and quench velocity in narrow rectangular channel of novel plate-type reactor

Xu, Wei, Guo, Jiuyuan, Liu, Xiaojing, Xiong, Jinbiao, Chai, Xiang, Zhang, Tengfei, Cheng, Xu, Zeng, Wei

Journal:

Annals of Nuclear Energy

Year:

2019

Language:

english

File:

PDF, 546 KB

english, 2019

33

Numerical investigation of thermal-hydraulic behaviors in a LBE-cooled 19-pin wire-wrapped rod bundle

Chai, Xiang, Liu, Xiaojing, Xiong, Jinbiao, Cheng, Xu

Journal:

Progress in Nuclear Energy

Year:

2019

Language:

english

File:

PDF, 2.30 MB

english, 2019

34

Investigation on interphase force modeling for vertical and inclined upward adiabatic bubbly flow

Jin, Di, Xiong, Jinbiao, Cheng, Xu

Journal:

Nuclear Engineering and Design

Year:

2019

Language:

english

File:

PDF, 2.44 MB

english, 2019

35

Lagrangian simulation of three-dimensional macro-scale melting based on enthalpy method

Xiong, Jinbiao, Zhu, Yingzi, Zhang, Tengfei, Cheng, Xu

Journal:

Computers & Fluids

Year:

2019

Language:

english

File:

PDF, 3.57 MB

english, 2019

36

Experimental study of cross flow and lateral pressure drop in a 5 × 5 rod bundle with mixing vane spacer grid

Qu, Wenhai, Wang, Zefeng, Xiong, Jinbiao, Cheng, Xu

Journal:

Nuclear Engineering and Design

Year:

2019

Language:

english

File:

PDF, 17.35 MB

english, 2019

37

Lagrangian simulation of three-dimensional macro-scale melting based on enthalpy method

Xiong, Jinbiao, Zhu, Yingzi, Zhang, Tengfei, Cheng, Xu

Journal:

Computers & Fluids

Year:

2019

File:

PDF, 3.57 MB

2019

38

Experimental and analytical study on heat dissipation mechanisms during spent fuel unloading in sodium fast reactor

Xiong, Jinbiao, Wu, Zenghui, Chen, Xiang, Zhang, Tengfei

Journal:

Annals of Nuclear Energy

Year:

2020

File:

PDF, 2.84 MB

2020

39

Preliminary safety analysis for the SCWR‐FQT facility

Liu, Xiaojing, Yang, Ting, Chai, Xiang, Xiong, Jinbiao, Zhang, Tengfei, Cheng, Xu

Journal:

International Journal of Energy Research

Year:

2019

Language:

english

File:

PDF, 2.82 MB

english, 2019

40

Preliminary safety analysis for the SCWR‐FQT facility

Liu, Xiaojing, Yang, Ting, Chai, Xiang, Xiong, Jinbiao, Zhang, Tengfei, Cheng, Xu

Journal:

International Journal of Energy Research

Year:

2019

File:

PDF, 2.82 MB

2019

41

Experimental investigation on transient boiling heat transfer during quenching of fuel cladding surfaces

Xiong, Jinbiao, Wang, Zefeng, Xiong, Ping, Lu, Tao, Yang, Yanhua

Journal:

International Journal of Heat and Mass Transfer

Year:

2019

File:

PDF, 3.63 MB

2019

42

Numerical investigation of flow blockage accident in SFR fuel assembly

Chai, Xiang, Zhao, Lei, Hu, Wenjun, Yang, Yun, Liu, Xiaojing, Xiong, Jinbiao, Cheng, Xu

Journal:

Nuclear Engineering and Design

Year:

2020

File:

PDF, 9.56 MB

2020

43

Can We Predict Response to Vagus Nerve Stimulation in Intractable Epilepsy

Xiong, Jinbiao, Cao, Yiyao, Yang, Weidong, Chen, Zhijuan, Yu, Qing

Journal:

International Journal of Neuroscience

Year:

2020

Language:

english

File:

PDF, 691 KB

english, 2020

44

Validation for CFD Simulation in Rod Bundles With Split-Vane Spacer Grids Based on LDA Measurement

Xiong, Jinbiao, Lu, Chuan, Qu, Wenhai

Journal:

Frontiers in Energy Research

Year:

2020

Language:

english

File:

PDF, 1.47 MB

english, 2020

45

Assessment of RANS models in predicting mixing flow induced by split-type vanes in rod bundle

Xiong, Jinbiao, Lu, Chuan, Qu, Wenhai, Yang, Yanhua, Cheng, Xu

Journal:

Nuclear Engineering and Design

Year:

2020

File:

PDF, 17.54 MB

2020

46

Comparisons of Reduced Moderation Small Modular Reactors With Heavy Water Coolant

Zhang, Tengfei, Liu, Xiaojing, Xiong, Jinbiao, Cheng, Xu

Journal:

Frontiers in Energy Research

Year:

2020

File:

PDF, 557 KB

2020

47

Numerical Investigation of Turbulent Heat Transfer Properties at Low Prandtl Number

Chai, Xiang, Liu, Xiaojing, Xiong, Jinbiao, Cheng, Xu

Journal:

Frontiers in Energy Research

Year:

2020

File:

PDF, 1.54 MB

2020

48

Serum-Derived Exosomes-Mediated Circular RNA ARHGAP10 Modulates the Progression of Non-Small-Cell Lung Cancer Through the miR-638/FAM83F Axis

Fang, Ke, Chen, Xuan, Qiu, Feng, Xu, Jinbiao, Xiong, Huanwen, Zhang, Zhanmin

Journal:

Cancer Biotherapy & Radiopharmaceuticals

Year:

2020

File:

PDF, 1.37 MB

2020

49

Verification and validation of MPS potential force interface tension model for stratification simulation

Zhu, Yingzi, Qiu, Zhifang, Xiong, Jinbiao, Yang, Yanhua

Journal:

Annals of Nuclear Energy

Year:

2020

File:

PDF, 7.91 MB

2020

50

MPS eutectic reaction model development for severe accident phenomenon simulation

Zhu, Yingzi, Xiong, Jinbiao, Yang, Yanhua

Journal:

Nuclear Engineering and Technology

Year:

2020

File:

PDF, 2.40 MB

2020