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全部论文审稿周期
10 篇有效样本 · 按发表日期由新到旧排列
审稿天数=录用日期-收稿日期；保留 PDF/DOI/网页源链接
86
天
Numerical investigation of thermal-hydraulic behavior in LBE-Cooled fast reactor assembly under ocean conditions via UDF-Enhanced CFD model
作者Yu Zhu; Kefan Zhang; Wenshun Duan; Sifan Dong; Hongli Chen
作者单位School of Nuclear Science and Technology, University of Science and Technology of China, Hefei, Anhui 230026, China
154
天
An efficient method for fault tree analysis to support nuclear plant operation decision-making
作者Mohamed Y. Nassar; Joseph O’Leary; Yunfei Zhao
作者单位Risk and Decision Analysis Laboratory, Department of Mechanical Engineering, University of Maryland, Glenn L. Martin Hall, 4298 Campus Dr., College Park, MD, 20742, United States; Center for Risk and Reliability, University of Maryland, Glenn L. Martin Hall, 4298 Campus Dr., College Park, MD, 20742, United States
70
天
A coupled three-dimensional porous-media and drift-flux model for full-domain thermal-hydraulic analysis of steam generators
作者Bo Wang; Yan Zhang; Zhiwei Huang; Yang Yang; Zhengrong Guo; Yukang Liu; Mingyang Li
作者单位Nuclear Equipment Design Institute, Dongfang Electric Corporation Limited, Chengdu 610097, China; Key Laboratory of Low-grade Energy Utilization Technologies and Systems, Ministry of Education of PRC, Chongqing University, 174 Shazheng District, Chongqing 400030, China; School of Energy and Power Engineering, Chongqing University, Chongqing 400030, China
65
天
Experimental and numerical study on the protective performance of special doors in nuclear power plants subjected to windborne missile impact and long-duration blast loading
作者Peng Xu; Xunjia Zhuo; He Zhu; De Chen
作者单位College of Civil Engineering, Tongji University, Shanghai 200092, China; Shenzhen China Nuclear Power Design Co., Ltd., Shenzhen 518172, China; State Key Laboratory of Nuclear Power Safety Technology and Equipment, China Nuclear Power Engineering Co., LV, Shenzhen 518116, China; School of Mechanics and Engineering Science, Shanghai University, Shanghai 200444, China
147
天
Studies of oxygen control in a lead–bismuth eutectic loop
作者Hui Li; Xiaoyang Lun; Wei Mao; Xingyan Zhou; Haicai Lyu; Huiping Zhu; Fang Liu; Ruixian Liang; Xiaobo Li; Fenglei Niu
作者单位Institute of Nuclear Energy Safety Technology, Hefei Institutes of Physical Science, Chinese Academy of Sciences, Hefei 230031, China; School of Nuclear Science and Engineering, North China Electric Power University, Beijing 102206, China; Institute of Modern Physics, Chinese Academy of Sciences, Lanzhou 730000, China
252
天
Comparison of control rod worth and doubling time in the high flux reactor: Static and dynamic Serpent 2 simulations with ENDF/B-VIII.0 and JEFF-3.3
作者Alan Wichink Kruit; Benjaminas Marcinkevicius; Kornilios Routsonis
作者单位NRG PALLAS, Westerduinweg 3, P.O. Box 25, 1755 ZG Petten, The Netherlands
56
天
58
天
Development of a neutronics–thermal–fluid–structure coupling methodology for performance analysis of U-50Zr helical cruciform fuel
作者Jianfeng Xu; Qufei Song; Tenglong Cong; Hui Guo; Hanyang Gu
作者单位School of Nuclear Science and Engineering, Shanghai Jiao Tong University, 800 Dongchuan Road, Shanghai, 200240, China
62
天
Performance mechanism and reliable operating regime of high-temperature sodium heat pipes with a large aspect ratio for MHPRs
作者Kun Li; Yan Yan; Xujia Wang; Quan Zhou; Kai Zhang; Qiming Men; Shengyao Jiang; Nan Gui
作者单位Shanghai Nuclear Engineering Research and Design Institute Co., Ltd., Shanghai 200233, China; Institute of Nuclear and New Energy Technology, Collaborative Innovation Center of Advanced Nuclear Energy Technology, Key Laboratory of Advanced Reactor Engineering and Safety, Ministry of Education, Tsinghua University, Beijing 100084, China
165
天
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样本口径2026 年最近 5 篇有效论文样本
平均审稿96.4 天
中位数77 天