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Chen Zeng
Observed name:
Chen ZENG
Institution:
Shanghai Nuclear Engineering Research and Design Institute (China)
Observed institutions:
Southwest University of Science and Technology,
Harbin Engineering University,
Shanghai Jiao Tong University,
Shanghai Nuclear Engineering Research and Design Institute (China),
The University of Tokyo
ORCID:
0000-0002-9843-2316
Observed ORCID:
0000-0002-9843-2316
OpenAlex ID:
A5024585345
Enhancement of mechanical, tribological and morphological properties of nitrogenated diamond-like carbon films by gradient nitrogen doping
2017
·
Chen Zeng
, Qingyun Chen
, et al.
·
Diamond and Related Materials
·
32
Preliminary control strategies of megawatt-class gas-cooled space nuclear reactor with different control rod configurations
2019
·
Tao Meng
, Kun Cheng
, et al.
·
Progress in Nuclear Energy
·
28
Experimental study on heat transfer and flow resistance performance of a microchannel heat exchanger with zigzag flow channels
2022
·
Xiang Zhou
, Chen Zeng
, et al.
·
Progress in Nuclear Energy
·
22
Experimental study on heat transfer and pressure drop characteristics in a microchannel heat exchanger assembly with S-shaped fins
2022
·
Chen Zeng
, Yinxi Song
, et al.
·
Applied Thermal Engineering
·
17
Optimization of the TRISO fuel particle distribution based on octahedral and icosahedral-based segmentation methods in the pebble-bed nuclear core
2020
·
Maolong Liu
, Chen Zeng
, et al.
·
International Journal of Advanced Nuclear Reactor Design and Technology
·
17
PDF
Effect of SiN interlayer thickness on adhesion and friction properties of diamond-like carbon films
2019
·
Qingyun Chen
, Chen Zeng
, et al.
·
Diamond and Related Materials
·
15
Performance evaluation of DRACS system of molten salt reactors using a transient solidification model
2021
·
Chen Zeng
, Xiao Chu
, et al.
·
Nuclear Engineering and Design
·
14
Optimization of the thermal-hydraulic performance of zigzag-type microchannel heat exchangers using asymmetric geometry
2022
·
Chen Zeng
, Yinxi Song
, et al.
·
Applied Thermal Engineering
·
13
A simplified method for calculating the heat rejection from a rectangle droplet sheet
2018
·
Chen Zeng
, Sichao Tan
, et al.
·
International Journal of Heat and Mass Transfer
·
12
Neutronics analysis of megawatt-class gas-cooled space nuclear reactor design
2019
·
Tao Meng
, Fulong Zhao
, et al.
·
Journal of Nuclear Science and Technology
·
11
Application of droplet motion and phase change model in containment spray system
2019
·
Fulong Zhao
, Xiao Yan
, et al.
·
Annals of Nuclear Energy
·
11
Evaluation of a freeze-tolerant decay heat removal system redundancy for fluoride salt-cooled high-temperature reactors (FHR)
2021
·
Maolong Liu
, Chen Zeng
, et al.
·
Annals of Nuclear Energy
·
7
Development and validation of a one-dimensional solidification model — Part I: Analytical model
2023
·
Chen Zeng
, Maolong Liu
, et al.
·
Annals of Nuclear Energy
·
6
Development and validation of a one-dimensional solidification model — Part II: Model validation for molten lead-bismuth
2023
·
Chen Zeng
, Maolong Liu
, et al.
·
Annals of Nuclear Energy
·
5
Droplet Motion and Phase Change Model with Two-Way Coupling
2019
·
Fulong Zhao
, Qianfeng Liu
, et al.
·
Journal of Thermal Science
·
5
Application of droplet motion and evaporation model in fuel spray in the constant volume bomb
2019
·
Tao MENG
, Xiao YAN
, et al.
·
Journal of Thermal Science and Technology
·
5
PDF
Transient thermal hydraulic analysis of a small passive lead–bismuth eutectic cooled fast reactor
2024
·
Chen Zeng
, Cong Shen
, et al.
·
Annals of Nuclear Energy
·
4
Liquid-fueled molten salt reactors: A comprehensive review on safety features and deterministic safety analysis
2026
·
Chen Zeng
, Chuntao Tang
, et al.
·
Progress in Nuclear Energy
·
2
A dynamic characteristic on the boiling crisis in downward facing flow boiling, Part II: Model development and validation
2024
·
Shixian Wang
, Kai Wang
, et al.
·
International Communications in Heat and Mass Transfer
Development of a solidification blockage discriminant model in filling pipelines
2024
·
Chen Zeng
, Cong Shen
, et al.
·
Annals of Nuclear Energy
Study on Freezing Tolerance Design of the Direct Reactor Auxiliary Cooling System (dracs) for Fluoride-salt-cooled High-temperature Reactor (fhr)
2023
·
Chen Zeng
, Hao Lin
, et al.
·
The Proceedings of the International Conference on Nuclear Engineering (ICONE)
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Works count:
21
Citation count:
226
H-index:
11
I10-index:
11
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