Fuel Cladding | List of Frontiers open access articles

Original Research

Published on 10 Aug 2021

Computational Geometry-Based 3D Yarn Path Modeling of Wound SiCf/SiC-Cladding Tubes and Its Application to Meso-Scale Finite Element Model

in Mechanics of Materials

Jianbo Tang
Gang Zhao
Jun Wang
Yue Ding
Yajie Feng
Yunsheng Chen
Chao Zhang
Qing Huang
Shiqing Xin
Jian Xu

Frontiers in Materials

doi 10.3389/fmats.2021.701205

3,503 views
14 citations

Original Research

Published on 23 Feb 2021

Friction and Wear Properties of CrAl-Based Coatings for Nuclear Fuel Cladding

in Nuclear Energy

Biao Ma
Bin Luo
Zhuozheng Wang
Chuiyi Meng
Xiujie He

Frontiers in Energy Research

doi 10.3389/fenrg.2021.622708

3,142 views
7 citations

Review

Published on 04 Mar 2022

Fission Gas Behaviors and Relevant Phenomena in Different Nuclear Fuels: A Review of Models and Experiments

in Nuclear Energy

Jingyu Guo
Huansheng Lai
Wenzhong Zhou
Jie Wei

Frontiers in Energy Research

doi 10.3389/fenrg.2022.766865

11,394 views
20 citations

Original Research

Published on 12 Apr 2022

Research on Thermal-Hydraulic Parameter Prediction Method of the Small Lead–Bismuth Fast Reactor Core Based on Adaptive RBF Neural Network

in Nuclear Energy

Hong Wu
Ren Li
Pengcheng Zhao
Tao Yu
Yanan Zhao

Frontiers in Energy Research

doi 10.3389/fenrg.2022.852146

3,039 views
4 citations

Mini Review

Published on 17 Nov 2022

Overview on performance degradation behavior of 20Cr25NiNb steel for gas cooled reactor cladding during service

in Environmental Degradation of Materials

Ming Shu
Yongduo Sun
Qin Zhou
Jun Xiao
Zhaodandan Ma
Xiao Liu

Frontiers in Materials

doi 10.3389/fmats.2022.1058045

4,027 views
4 citations

Original Research

Published on 08 Feb 2021

Multiscale Modeling of SiCf/SiC Nuclear Fuel Cladding Based on FE-Simulation of Braiding Process

in Environmental Degradation of Materials

Yajie Feng
Jun Wang
Nianwei Shang
Gang Zhao
Chao Zhang
Jianbo Tang
Shiqing Xin
Andreas Hornig
Maik Gude
Qing Huang

Frontiers in Materials

doi 10.3389/fmats.2020.634112

5,509 views
11 citations

Original Research

Published on 09 Jun 2021

Coupled Modeling and Simulation of Phase Transformation in Zircaloy-4 Fuel Cladding Under Loss-of-Coolant Accident Conditions

in Nuclear Energy

Wenjun Lu
Libo Qian
Wenzhong Zhou

Frontiers in Energy Research

doi 10.3389/fenrg.2021.667419

2,675 views
1 citation

Methods

Published on 28 May 2021

Effects of U-Mo Irradiation Creep Performance on the Thermo-Mechanical Coupling Behavior in U-Mo/Al Monolithic Fuel Assemblies

in Nuclear Energy

Xiaoxiao Mao
Xiaobin Jian
Jingyu Zhang
Feng Yan
Shurong Ding
Yongzhong Huo
Haoyu Wang
Lin Zhang
Yuanming Li

Frontiers in Energy Research

doi 10.3389/fenrg.2021.676881

2,624 views
7 citations

Articles

Computational Geometry-Based 3D Yarn Path Modeling of Wound SiCf/SiC-Cladding Tubes and Its Application to Meso-Scale Finite Element Model

Friction and Wear Properties of CrAl-Based Coatings for Nuclear Fuel Cladding

Fission Gas Behaviors and Relevant Phenomena in Different Nuclear Fuels: A Review of Models and Experiments

Research on Thermal-Hydraulic Parameter Prediction Method of the Small Lead–Bismuth Fast Reactor Core Based on Adaptive RBF Neural Network

Overview on performance degradation behavior of 20Cr25NiNb steel for gas cooled reactor cladding during service

Multiscale Modeling of SiCf/SiC Nuclear Fuel Cladding Based on FE-Simulation of Braiding Process

Coupled Modeling and Simulation of Phase Transformation in Zircaloy-4 Fuel Cladding Under Loss-of-Coolant Accident Conditions

Effects of U-Mo Irradiation Creep Performance on the Thermo-Mechanical Coupling Behavior in U-Mo/Al Monolithic Fuel Assemblies