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1
Evelopment Characteristics and Inspiration of Marine Nuclear Power
Lu Chuan, Wang Zhonghui, Yu Junchong
2022, 43(1): 1-6. doi: 10.13832/j.jnpe.2022.01.0001
Abstract(2955) HTML(717) PDF(2950) [Cited by] (6)
2
Digital Reactor: Development and Challenges
Yu Hongxing, Li Wenjie, Chai Xiaoming, Li Songwei
2020, 41(4): 1-7.
Abstract(1451) PDF(1392) [Cited by] (14)
3
Nuclear Power AI Applications: Status, Challenges and Opportunities
Zhang Heng, Lyu Xue, Liu Dong, Wang Guoyin, Hang Qin, Sha Rui, Guo Bin
2023, 44(1): 1-8. doi: 10.13832/j.jnpe.2023.01.0001
Abstract(9859) HTML(748) PDF(1208) [Cited by] (5)
4
Key Technology of ACP100: Reactor Core and Safety Design
Song Danrong, Li Qing, Qin Dong, Dang Gaojian, Zeng Chang, Li Song, Xiao Renjie, Wei Xuedong
2021, 42(4): 1-5. doi: 10.13832/j.jnpe.2021.04.0001
Abstract(5295) HTML(1359) PDF(909) [Cited by] (7)
5
Present Situation and Prospect of Radioactive Waste Liquid Treatment Technology
Sun Shouhua, Ran Mingdong, Lin Li, Liu Wenlei, Li Zhenchen, Li Wenyu
2019, 40(6): 1-6. doi: 10.13832/j.jnpe.2019.06.0001
Abstract(1523) PDF(812) [Cited by] (48)
6
Research on the Development Trend of Micro Nuclear Reactor Technology
Du Shuhong, Li Yonghua, Sun Tao, Wang Jun, Liu Xiaowen, Su Gang, Zhao Depeng
2022, 43(4): 1-4. doi: 10.13832/j.jnpe.2022.04.0001
Abstract(2308) HTML(413) PDF(725) [Cited by] (9)
7
Initiation and Development of Heat Pipe Cooled Reactor
Yu Hongxing, Ma Yugao, Zhang Zhuohua, Chai Xiaoming
2019, 40(4): 1-8.
Abstract(1927) PDF(618) [Cited by] (72)
8
Solving Multi-Dimensional Neutron Diffusion Equation Using Deep Machine Learning Technology Based on PINN Model
Liu Dong, Luo Qi, Tang Lei, An Ping, Yang Fan
2022, 43(2): 1-8. doi: 10.13832/j.jnpe.2022.02.0001
Abstract(3740) HTML(638) PDF(603) [Cited by] (12)
9
Thoughts on the Application of Artificial Intelligence in Nuclear Energy Field
Tan Sichao, Li Tong, Liu Yongchao, Liang Biao, Wang Bo, Shen Jihong
2023, 44(2): 1-8. doi: 10.13832/j.jnpe.2023.02.0001
Abstract(2923) HTML(153) PDF(584) [Cited by] (8)
10
CFD Investigation on Flow and Heat Transfer Characteristics of Fuel Assembly for VVER Reactor
Wang Xiong, Du Daiquan, Zeng Xiaokang, Yang Xiaoqiang, Zan Yuanfeng
2018, 39(3): 6-9. doi: 10.13832/j.jnpe.2018.03.0006
Abstract(1473) PDF(570) [Cited by] (4)
11
Radiation Safety System and Its Design Coordination for Nuclear-Powered Ship
Lin Xiaoling
2019, 40(5): 1-5.
Abstract(649) PDF(566) [Cited by] (1)
12
Development and Prospect of Advanced Nuclear Energy Technology
Wang Conglin, Chai Xiaoming, Yang Bo, Li Zhongchun
2023, 44(5): 1-5. doi: 10.13832/j.jnpe.2023.05.0001
Abstract(2667) HTML(262) PDF(495) [Cited by] (31)
13
Design and Verification of Acoustic Leak Monitoring System for Nuclear Power Plants
Zhou Zhengping
2018, 39(3): 110-113. doi: 10.13832/j.jnpe.2018.03.0110
Abstract(1047) PDF(429) [Cited by] (6)
14
Study on Dynamic Characteristics of Xi’an Pulsed Reactor under Non-Pulse Transient Condition
Zhang Liang, Yuan Jianxin, Zhao Wei, Wang Baosheng, Zhang Qiang, Zhu Guangning, Jiang Xinbiao, Chen Lixin
2020, 41(5): 1-7.
Abstract(552) PDF(401) [Cited by] (4)
15
Study on JFNK Global Solution Method of of Full-core Thermal Sub-channel Model
Zhang Yunshan, Zhou Xiafeng
2023, 44(5): 39-46. doi: 10.13832/j.jnpe.2023.05.0039
Abstract(1810) HTML(278) PDF(392) [Cited by] (1)
16
Evalution and Application of Probabilistic Safety Assessment in Nuclear Energy Safety Analysis
Yu Hongxing, Wu Lingjun, Deng Chunrui, Deng Jian, Lu Yili, Zhang Hang, Peng Huanhuan, Wang Xiaoji
2020, 41(6): 1-7.
Abstract(751) PDF(391) [Cited by] (6)
17
Simulation Model Architecture and Concept Validation for Thermal Hydraulic Characteristics of Two-Phase Fluid Based on Modelica
Huang Yanping, Zeng Xiaokang, Ding Ji
2021, 42(1): 1-7. doi: 10.13832/j.jnpe.2021.01.0001
Abstract(1896) PDF(387) [Cited by] (8)
18
Research Progresses of Uncertainty Quantification Methods for High Fidelity Numerical Nuclear Reactor
Cao Liangzhi, Zou Xiaoyang, Liu Zhouyu, Wan Chenghui, Wu Hongchun
2021, 42(2): 1-15. doi: 10.13832/j.jnpe.2021.02.0001
Abstract(2032) PDF(375) [Cited by] (13)
19
Approximate Analysis of Temperature for Thermal Insulation Structure of Nuclear Main Pump
Xu Shengli, Zhang Jin, Zhong Shaowei, Xiao Zhonghui
2018, 39(3): 1-5. doi: 10.13832/j.jnpe.2018.03.0001
Abstract(1104) PDF(369) [Cited by] (16)
20
Research Progress of Hearth Monitoring and Fault Diagnosis for Reactor Critical Equipment
Liu Caixue, Luo Neng, He Pan, Liu Jiaxin, Peng Cuiyun
2023, 44(3): 8-20. doi: 10.13832/j.jnpe.2023.03.0008
Abstract(3070) HTML(200) PDF(320) [Cited by] (7)
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