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Annals of Nuclear Energy (0306-4549) | AMiner期刊详情 | AMiner
Annals of Nuclear Energy
Journal
ISSN 0306-4549
eISSN 1873-2100
中科院 工程技术 3区
年发文量
研究主题
论文（13272）
排序
时间
引用
1
New
Prompt Neutron Spectrum from 237np(n,f) Reaction at 〈en〉=3 MeV
G. Mishra
,
Sukanya De
,
G. Mohanto
,
Ajay Kumar
,
R. Tripathi
,
R.G. Thomas
2027
引用
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2
New
Numerical Investigation of Thermal-Hydraulic Behavior in LBE-Cooled Fast Reactor Assembly under Ocean Conditions Via UDF-Enhanced CFD Model
Yu Zhu
,
Kefan Zhang
,
Wenshun Duan
,
Sifan Dong
,
Hongli Chen
2027
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3
New
Numerical Investigation of Interfacial Stability and Crack-Induced Cohesive Degradation in Cr-coated Zircaloy-4 Cladding under LOCA Conditions
Jinkai Zhang
,
Zhaohao Wang
,
Zhenhong Ge
,
Di Yun
,
Wenbo Liu
2027
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4
New
Multiphysics Coupled Thermal-to-electric Performance Analysis of a Stirling-type Heat Pipe Reactor System
Aoguang Wu
,
Weixiang Wang
,
Kefan Zhang
,
Xiao Luo
,
Hongli Chen
2027
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5
New
ZnO-rich Borate-Titanate Glasses Engineered with Eu3+ and Ba2+ for Improved Optical Features and Gamma-Ray Shielding Properties
M.I. Sayyed
,
Manjunatha
,
Sulochana P. Melinmath
,
Shams A.M. Issa
,
P.B.Ranjith Gowda
,
A.S. Bennal
2027
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6
New
Uncertainty-aware Superpixel Segmentation and Bayesian Optimization for Sampling Strategy Development Using Activation Analysis of OPR-1000
Jeongon Eom
,
Sewon Kim
,
Seokjun Hong
,
Changje Park
2027
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7
New
Development and Application of Three-Dimensional Thermal–hydraulic Code for Pebble Bed High-Temperature Gas-Cooled Reactor
Liu Ming
,
Song Qingkang
,
Wu Pan
,
Li Sheng
,
Liu Wei
,
Feng Xing
,
Wu Zhao
,
Shan Jianqiang
2027
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8
New
Effect of Thermal-Hydraulic Model Simplifications on Steady-State Temperature Distributions in the MSRE
Long He
,
Shaoru Zhang
,
Jiajie Shen
,
Yu Huang
2027
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9
New
Effects of Applied Load on Microstructure and Corrosion Behavior of Sensitized 304H Stainless Steel Treated by Ultrasonic Nanocrystalline Surface Modification (UNSM)
Jinwook Choi
,
J.P. Lacy
,
Carson Lukas
,
Kasturi Sasidhar
,
Kumar Sridharan
,
Hwasung Yeom
2027
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10
New
Characterizing Self-Attenuation in UO2 Powder Gamma Spectrometry: Development of a Matrix-Independent Assay for Mass and Enrichment Quantification in Bulk Nuclear Material⋆
Mohamad Sukron F. Husein
,
Mohammad Subekti
,
Sihana
,
Didik Setiaji
,
Agus. Sunarto
,
Fajar M. Ramadhan
,
Mohammad Alfarisie
,
Etty Mutiara
,
Ahadi D. Prasetya
,
Erlina Noerpitasari
2027
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11
New
A Coupled Three-Dimensional Porous-Media and Drift-Flux Model for Full-Domain Thermal-Hydraulic Analysis of Steam Generators
Bo Wang
,
Yan Zhang
,
Zhiwei Huang
,
Yang Yang
,
Zhengrong Guo
,
Yukang Liu
,
Mingyang Li
2027
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12
New
Studies of Oxygen Control in a Lead–bismuth Eutectic Loop
Hui Li
,
Xiaoyang Lun
,
Wei Mao
,
Xingyan Zhou
,
Haicai Lyu
,
Huiping Zhu
,
Fang Liu
,
Ruixian Liang
,
Xiaobo Li
,
Fenglei Niu
2027
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13
New
Environmental Performance of Clay-Based Barriers for Radioactive Waste Disposal: a Review with Relevance to Portuguese Geological Materials
Paula Galego Fernandes
,
M. Isabel Dias
,
José Marques
2027
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14
New
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
Peng Xu
,
Xunjia Zhuo
,
He Zhu
,
De Chen
2027
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15
New
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
Alan Wichink Kruit
,
Benjaminas Marcinkevicius
,
Kornilios Routsonis
2027
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16
New
Research on System Operation Control Method for SMRs Based on Main Pump Health Assessment
Kai Wang
,
Zhi Chen
,
Pengcheng Yang
,
Yaowu Li
,
Yifan Jian
,
Xuecen Zhao
2027
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17
New
Performance Mechanism and Reliable Operating Regime of High-Temperature Sodium Heat Pipes with a Large Aspect Ratio for MHPRs
Kun Li
,
Yan
,
Xujia Wang
,
Quan Zhou
,
Kai Zhang
,
Qiming Men
,
Shengyao Jiang
,
Nan Gui
2027
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18
New
Fuel-form Effects on Normal-Operation and LOCA Performance of U–ZrH and MOX Fuel Rods in the MARVEL Microreactor
Yuze Tan
,
Rong Liu
2027
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19
New
Development of a Neutronics–thermal–fluid–structure Coupling Methodology for Performance Analysis of U-50Zr Helical Cruciform Fuel
Jianfeng Xu
,
Qufei Song
,
Tenglong Cong
,
Hui Guo
,
Hanyang Gu
2027
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20
New
On the Reported Critical-Heat-flux Enhancement of Helical Fuel: Comparison Basis, Correction-Factor Consistency, and Look-Up-table Uncertainty
Hamza Zeghari
2027
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加载更多
高被引作者
作者
引用
发文
Guanghui Su
4172
222
Suizheng Qiu
3853
228
M.M.R. Williams
3749
150
Wenxi Tian
3465
209
Jaakko Leppänen
2540
33
D. H. Wright
2002
1
Benoit Forget
1788
45
Ville Valtavirta
1680
22
Maria Pusa
1635
6
tuomas viitanen
1454
4
高产作者
作者
引用
发文
Suizheng Qiu
3853
228
Guanghui Su
4172
222
Wenxi Tian
3465
209
Liangzhi Cao
1418
154
M.M.R. Williams
3749
150
Hongchun Wu
1380
142
Hanyang Gu
982
106
Kan Wang
1172
83
Sichao Tan
826
83
Ruifeng Tian
330
70
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