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Progress in Nuclear Energy
IF
3.2
论文数
5671
被引数
9957
相关解读
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期刊论文
5671
相关解读
0
期刊论文
5671
发表时间
发表时间
IF
被引数
Dissolution model and experimental verification of lead oxide for solid-state oxygen control in lead-bismuth coolant
铅氧化物用于铅铋冷却剂固态氧控制的溶解模型与实验验证
Progress in Nuclear Energy
IF
3.2
2026-10-28
0
PRE
AI
Xian Zeng; Jinyu Yue; Peng Lin; Ziyi Liang; Yang Zhang; Qingzhi Yan
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Staffing the nuclear renaissance: An integrated modeling assessment of national workforce requirements for Canada’s 2050 nuclear expansion
为核复兴配备人员:加拿大2050年核能扩张所需国家劳动力的综合模型评估
Progress in Nuclear Energy
IF
3.2
2026-10-26
0
OA
AI
Michael Tadrous; David Novog; Goran Calic
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Passive safety in prismatic HTGRs: A comprehensive review of thermal hydraulics, natural circulation, and heat transfer mechanisms
棱柱型高温气冷堆的固有安全性:热工水力学、自然循环和传热机制的全面综述
Progress in Nuclear Energy
IF
3.2
2026-10-26
0
PRE
AI
Ahmed Jasim; Farooq Ahmed; Shoaib Usman; Rahman Almusafir; Muthanna Al-Dahhan
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Comparative analysis of offsite consequence results based on ICRP 26, ICRP 60, and ICRP 103 frameworks in level 3 PSA
基于ICRP 26、ICRP 60和ICRP 103框架的第三级PSA中厂外后果结果的比较分析
Progress in Nuclear Energy
IF
3.2
2026-10-26
0
OA
AI
Dakyoung Lee; Sung-yeop Kim; Eung Soo Kim
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Research on continuous-energy nuclear data assimilation methods and its application on China Experimental Fast Reactor (CEFR)
连续能量核数据同化方法研究及其在中国实验快堆(CEFR)上的应用
Progress in Nuclear Energy
IF
3.2
2026-10-26
0
PRE
AI
Qingming He; Jinlong Huang; Mohan Wang; Liangzhi Cao; Hongchun Wu
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Quantitative evaluation of backend nuclear fuel cycle metrics for an HTGR-based SMR compared with a conventional large PWR
基于高温气冷反应堆的SMR与常规大型PWR的后端核燃料循环指标定量评估
Progress in Nuclear Energy
IF
3.2
2026-10-24
0
PRE
AI
Ji Su Kang; Jae Hak Cheong
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Deterministic double-layer sampling with surrogate-assisted adverse case identification for reactor BEPU analysis
基于代理辅助不利案例识别的确定性双层采样方法在反应堆BEPU分析中的应用
Progress in Nuclear Energy
IF
3.2
2026-10-24
0
PRE
AI
Mengyan Hu; Yubo Qi; Chengcheng Deng; Zongyang Li; Jun Yang
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Acid-resistant phosphinic amide-functionalized UiO-66-NH
2
(Ce) MOF for selective sequestration of Pu(IV) from highly acidic nuclear waste streams
耐酸性次膦酰胺功能化的UiO-66-NH
2
(Ce) MOF用于从强酸性核废料流中选择性富集Pu(IV)
Progress in Nuclear Energy
IF
3.2
2026-10-24
0
PRE
AI
D.B. Sharma; S.A. Ansari; A. Bhattacharyya; S. Bommkanti; G. Karmakar; A. Tyagi; A.K. Tyagi
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An economic assessment of naval nuclear fuel reprocessing for HALEU production: A public-private partnership model
对海军核燃料后处理用于HALEU生产的经济学评估:一种公私合作模式
Progress in Nuclear Energy
IF
3.2
2026-10-23
0
OA
AI
Mitchell Heaton; Robert Hayes
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A computational framework for analyzing flow blockage in plate-type fuel channels with two-phase flow and melt transport
用于分析两相流和熔体输运条件下板型燃料通道中流动阻塞的数值框架
Progress in Nuclear Energy
IF
3.2
2026-10-21
0
PRE
AI
Jie Zhang; Meng Lv; Heng Xie; Lei Shi
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Effects of curvature and inclination on external steam condensation with non-condensable gases under natural convection
曲率和倾斜度对自然对流条件下含非冷凝气体的外部蒸汽冷凝的影响
Progress in Nuclear Energy
IF
3.2
2026-10-16
0
PRE
AI
Ruihan Jing; Shuhang Zhou; Daiyong Song; Xu Zhang; Chao Jiang; Haozhi Bian; Jianjun Wang
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Proactive maintenance and structural modifications of VVER-1000 steam generator blowdown systems to ensure long-term safety
VVER-1000蒸汽发生器排污系统的主动维护与结构改造以确保长期安全
Progress in Nuclear Energy
IF
3.2
2026-10-16
0
PRE
AI
Karel Vidlák; Vladimír Mózer
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Numerical study on effects of tube bundle geometry and arrangement on external steam-air condensation
管束几何形状和排列对外部蒸汽-空气凝结影响的数值研究
Progress in Nuclear Energy
IF
3.2
2026-10-16
0
PRE
AI
Daiyong Song; Nan Zhang; Ruihan Jing; Qianru Liu; Zhongning Sun; Haozhi Bian
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Radiological characterization for research reactor decommissioning: Application of lessons learned from the VVR-S reactor to the WWR-M facility
研究堆退役的放射学表征:将VVR-S反应堆的经验教训应用于WWR-M设施
Progress in Nuclear Energy
IF
3.2
2026-10-13
0
PRE
AI
D. Gurau; Yu.M. Lobach; I.A. Maliuk
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Geometric fidelity, contact-point treatment, and thermal hydraulics in pebble-bed FHR: A review of pebble-bed modeling strategies
在球床FHR中几何保真度、接触点处理与热工水力学:球床建模策略综述
Progress in Nuclear Energy
IF
3.2
2026-10-11
0
PRE
AI
Guangyuan Jin; Chaoyi Chen; Yongxing Li; Hongye He; Yandong Hou
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A new method for calculating the weak source startup of reactor based on Monte Carlo method
基于蒙特卡罗方法计算反应堆弱源启动的新方法
Progress in Nuclear Energy
IF
3.2
2026-10-10
0
PRE
AI
Conglong Jia; Yuanhao Gou; Kan Wang; Shichang Liu
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Nuclear data-induced uncertainties in the neutron source for vessel fluence evaluations: Application to TVA-watts bar unit 1 cycle 1
核数据在反应堆容器中子注量评价中引发的不确定性:TVA-Watts Bar 1号机组1周期的应用
Progress in Nuclear Energy
IF
3.2
2026-10-10
0
OA
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Iñigo Gayo; Emilio Castro; Nuria García-Herranz; Oscar Cabellos; Kostadin Ivanov
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Impact of residual nuclides on the transmutation of Np and Am in a lead-cooled fast reactor
残留核素对铅冷快堆中Np和Am嬗变的影响
Progress in Nuclear Energy
IF
3.2
2026-10-09
0
PRE
AI
Yue Jiang; Zhiwen Wen; Shiyu Song; Junkui Xu; Yiwei Gong; Xiaoqin Tang; Yuxuan Huang; Xu Zhou; Liyingran Zeng; Xiang Hu; Jianling Ran; Sen Song; Peng Luo
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Experimental study on flow patterns and pressure oscillation characteristics of vertical upward steam jets at low water temperatures
低水温下垂直向上蒸汽射流的流型及压力振荡特性实验研究
Progress in Nuclear Energy
IF
3.2
2026-10-09
0
PRE
AI
Weiyu Chu; Jidong Cong; Zhaoming Meng; Ping Song; Yinghua Chai
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Thermo-fluid characteristics at the points of onset of nucleate boiling and onset of significant void in vertical upward boiling flows
垂直向上沸腾流中核态沸腾起始点和显著空泡起始点的热流体特性
Progress in Nuclear Energy
IF
3.2
2026-10-08
0
PRE
AI
Shichang Dong; Takashi Hibiki
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