Skip to Main Content
American Society of Mechanical Engineers: Digital Collection Open Menu
Cart
header search
Search
Advanced Search
Skip Nav Destination

Proceedings Papers

Proceedings Volume Cover
2022 29th International Conference on Nuclear Engineering
August 8–12, 2022
Virtual, Online
Conference Sponsors:
  • Nuclear Engineering Division
ISBN:
978-0-7918-8636-6
Volume 2: Nuclear Fuel and Material, Reactor Physics and Transport Theory, and Fuel Cycle Technology

Front Matter

ICONE29 Front Matter
ICONE 2022; V002T00A001https://doi.org/10.1115/ICONE29-FM2
View Articletitled, SCM.SharedControls.Infrastructure.TitleDisplayModel?.Text
PDF

Nuclear Fuel and Material, Reactor Physics and Transport Theory, and Fuel Cycle Technology

Research on Modeling Method and Eigenvalue Calculation of Single Dispersion of Fuel Particles
Anmin Yuan, Hongchun Wu, Yunzhao Li, Liangzhi Cao, Cong Wang, Chaofei Jiang, Shenzhi Yu, Yi Liao, Jinrong Qiu
ICONE 2022; V002T02A001https://doi.org/10.1115/ICONE29-88937
View Articletitled, SCM.SharedControls.Infrastructure.TitleDisplayModel?.Text
PDF
Topics: Eigenvalues , Fuels , Modeling , Particulate matter
Creep Performance and Microstructure Evolution of IN617 at 950 °C for VHTR Applications
Yue Wang, Haitao Wang, Kejian Li
ICONE 2022; V002T02A002https://doi.org/10.1115/ICONE29-88939
View Articletitled, SCM.SharedControls.Infrastructure.TitleDisplayModel?.Text
PDF
Topics: Creep , Very high temperature reactors
Preliminary Study on Corrosion Behavior and Mechanical Properties Of Inconel 617 in Impure Helium Environment of VHTR
Bin Du, Huaqiang Yin, Tao Ma, Haoxiang Li, Wei Zheng, Xuedong He
ICONE 2022; V002T02A003https://doi.org/10.1115/ICONE29-88943
View Articletitled, SCM.SharedControls.Infrastructure.TitleDisplayModel?.Text
PDF
Topics: Corrosion , Helium , Mechanical properties , Very high temperature reactors
A Bi-Layered Three-Dimensional Mechanical Modeling of the Cladding and Its Creep Deformation Analysis
Ming Zhang, Jinggang Li, Xiaohan Liu, Yong Lu, Yanan Zhu
ICONE 2022; V002T02A004https://doi.org/10.1115/ICONE29-88944
View Articletitled, SCM.SharedControls.Infrastructure.TitleDisplayModel?.Text
PDF
Topics: Cladding systems (Building) , Collapse , Creep , Modeling
Creep Properties of FeCrAl Alloy at High Temperature Under Neutron Irradiation
Huan Yao, Tianzhou Ye, Junmei Wu, Yingwei Wu, Chunyu Yin, Ping Chen
ICONE 2022; V002T02A005https://doi.org/10.1115/ICONE29-89079
View Articletitled, SCM.SharedControls.Infrastructure.TitleDisplayModel?.Text
PDF
Topics: Alloys , Creep , High temperature , Irradiation (Radiation exposure) , Neutrons
The Optimal Theta of Optimally Diffusive Coarse Mesh Finite Difference Method to Accelerate DGFEM Based SN
Boran Kong, Han Zhang, Kaijie Zhu, Chen Hao, Jiong Guo, Fu Li
ICONE 2022; V002T02A006https://doi.org/10.1115/ICONE29-89221
View Articletitled, SCM.SharedControls.Infrastructure.TitleDisplayModel?.Text
PDF
Topics: Diffusion (Physics) , Eigenvalues , Electromagnetic scattering , Finite difference methods , Fittings , Fourier analysis , Neutrons , Polynomials , Radiation scattering , Scattering (Physics)
Research on Scenarios and Development Paths of China’s Commercial Closed Nuclear Fuel Cycle
Min Xiao, Xiaojun Xiao
ICONE 2022; V002T02A007https://doi.org/10.1115/ICONE29-89223
View Articletitled, SCM.SharedControls.Infrastructure.TitleDisplayModel?.Text
PDF
Topics: Nuclear fuel cycle , Pressurized water reactors
Validation of NUIT for Decay Heat Predictions of PWR Spent Fuel Assemblies
Jian Li, Ruihan Li, Ding She, Jin'gang Liang, Lei Shi
ICONE 2022; V002T02A008https://doi.org/10.1115/ICONE29-89241
View Articletitled, SCM.SharedControls.Infrastructure.TitleDisplayModel?.Text
PDF
Topics: Heat , Pressurized water reactors , Spent nuclear fuels , Fuels , Neutrons , Boiling water reactors , Collapse , Cooling , Cross section (Physics) , Density
Analysis of Hydrogenation Properties of Nuclear Fuel Zirconium Alloy Cladding
Lin Qin
ICONE 2022; V002T02A009https://doi.org/10.1115/ICONE29-89580
View Articletitled, SCM.SharedControls.Infrastructure.TitleDisplayModel?.Text
PDF
Topics: Accidents , Cladding systems (Building) , Nuclear fuels , Zirconium alloys
Design of Radiation Damage Monitoring Scheme for Materials in China Experimental Fast Reactor
Hu Ziao, Chen Xiao-xian, Chen Xiao-liang
ICONE 2022; V002T02A010https://doi.org/10.1115/ICONE29-90146
View Articletitled, SCM.SharedControls.Infrastructure.TitleDisplayModel?.Text
PDF
Topics: China , Damage , Design , Fast neutron reactors , Irradiation (Radiation exposure) , Neutron flux , Radiation damage , Sensors , Neutrons , Cladding systems (Building)
Microstructural Evolution of SiC-Coated C/C Composites Under Argon Ion Irradiation
Xiangmin Xie, Long Yan, Guodong Cheng, Xian Tang
ICONE 2022; V002T02A011https://doi.org/10.1115/ICONE29-90325
View Articletitled, SCM.SharedControls.Infrastructure.TitleDisplayModel?.Text
PDF
Topics: Coatings , Composite materials , Irradiation (Radiation exposure)
Fuel Management Strategy of LBE-Cooled Fast Reactor BLESS-D
Zhen Luo, Eing Yee Yeoh, Xiaosong Chen, Linsen Li, Mian Xing
ICONE 2022; V002T02A012https://doi.org/10.1115/ICONE29-90443
View Articletitled, SCM.SharedControls.Infrastructure.TitleDisplayModel?.Text
PDF
Topics: Cycles , Equilibrium (Physics) , Fast neutron reactors , Fuel management
Criticality Safety Analysis of Fuel Storage Under Fuel Assembly Dropping Accident
Mingliang Dai, Pengtao Fu, Jun Zhao
ICONE 2022; V002T02A013https://doi.org/10.1115/ICONE29-90509
View Articletitled, SCM.SharedControls.Infrastructure.TitleDisplayModel?.Text
PDF
Topics: Accidents , Fuel storage , Fuels , Manufacturing , Safety
Molten Salt Reactor Experiment Simulation Using ThorMOC
Ao Zhang, Ming Dai, Maosong Cheng, Jingen Chen
ICONE 2022; V002T02A014https://doi.org/10.1115/ICONE29-90510
View Articletitled, SCM.SharedControls.Infrastructure.TitleDisplayModel?.Text
PDF
Topics: Molten salt reactors , Simulation , Modeling , Eigenvalues , Graphics processing units , Neutrons , Nuclear reactors
Mechanical Performance Assessment of Independently-Developed Zirconium Alloy Under RIA Condition
Jie Wang, Yang Wang, Jun Wei, Yongjun Deng
ICONE 2022; V002T02A015https://doi.org/10.1115/ICONE29-90521
View Articletitled, SCM.SharedControls.Infrastructure.TitleDisplayModel?.Text
PDF
Topics: Cladding systems (Building) , Ductility , Equipment performance , Hydrogen , Zirconium alloys , Zirconium , Accidents , Failure , Fracture (Process) , Light water reactors
Effect of a Cr2O3/A-Al2O3 Coating on the Corrosion Behavior of Incoloy 800H Alloy in High Temperature Impure Helium
Haoxiang Li, Wei Zheng, Bin Du, Huaqiang Yin, Zhihao Hong, Long Wang, Xuedong He, Tao Ma, Xingtuan Yang
ICONE 2022; V002T02A016https://doi.org/10.1115/ICONE29-90536
View Articletitled, SCM.SharedControls.Infrastructure.TitleDisplayModel?.Text
PDF
Topics: Alloys , Carburization , Coating processes , Coatings , Corrosion , Helium , High temperature
Automation of High-Fidelity Modeling of PWR Fuel Rods and Verification
Zhang Chunyu, Wang Yang, Deng Yongjun, Song Zifan, Lu Yong
ICONE 2022; V002T02A017https://doi.org/10.1115/ICONE29-90557
View Articletitled, SCM.SharedControls.Infrastructure.TitleDisplayModel?.Text
PDF
Topics: Finite element model , Fuel rods , Modeling , Pressurized water reactors
Neutronics Analysis of RBMK-1000 Reactor Using OpenMC: Criticality and Depletion Analysis at 3D Assembly Level
Mohammad Hashemi, Rafael Macián-Juan, Martin Ohlerich
ICONE 2022; V002T02A018https://doi.org/10.1115/ICONE29-90636
View Articletitled, SCM.SharedControls.Infrastructure.TitleDisplayModel?.Text
PDF
Topics: Manufacturing , Nuclear fission , Spent nuclear fuels , Chemical kinetics , Computer programming languages , Databases , Design , Nuclear power , Nuclear power stations , Parametric design
Experimental Study on Dynamic Tensile Strength of Graphite
Dongqing Tian, Li Shi, Libin Sun, Ke Shen, Kun Xu
ICONE 2022; V002T02A019https://doi.org/10.1115/ICONE29-90670
View Articletitled, SCM.SharedControls.Infrastructure.TitleDisplayModel?.Text
PDF
Topics: Graphite , Stress-strain curves , Tensile strength
Effect of Surface Treatment on the Corrosion Behavior of Stainless Steels in High-Temperature Supercritical Carbon Dioxide
Zhu Liu, Haozhan Su, Jiachen Long, Shuo Cong, Kai Chen, Xianglong Guo, Lefu Zhang
ICONE 2022; V002T02A020https://doi.org/10.1115/ICONE29-90718
View Articletitled, SCM.SharedControls.Infrastructure.TitleDisplayModel?.Text
PDF
Topics: Carburization , Corrosion , High temperature , Oxidation , Stainless steel , Supercritical carbon dioxide , Surface finishing
Hydrogenation of Zircaloy-4 in a Defective Fuel Pellet for Pressurized Water Reactors
Doctor Enivweru, Qingyu Wang, Abiodun Ayodeji, John Njoroge
ICONE 2022; V002T02A021https://doi.org/10.1115/ICONE29-90736
View Articletitled, SCM.SharedControls.Infrastructure.TitleDisplayModel?.Text
PDF
Topics: Corrosion , Fuels , Hydrogen embrittlement , Pressurized water reactors , Cladding systems (Building) , Hydrogen , Temperature , Accidents , Boundary-value problems , Coolants
Research on Cracked Fuel Relocation of Dual-Cooled Annular Fuel Element Under Normal and LOCA Conditions
Yangbin Deng, Yuan Yin
ICONE 2022; V002T02A022https://doi.org/10.1115/ICONE29-90755
View Articletitled, SCM.SharedControls.Infrastructure.TitleDisplayModel?.Text
PDF
Topics: Cracking (Materials) , Discrete element methods , Fracture (Process) , Fuels
Preparation Method of ORIGEN2 Library for High Temperature Gas-Cooled Reactors
Irwan Liapto Simanullang, Katsuki Fukuhara, Keisuke Morita, Yuji Fukaya, Hai Quan Ho, Satoru Nagasumi, Kazuhiko Iigaki, Etsuo Ishitsuka, Nozomu Fujimoto
ICONE 2022; V002T02A023https://doi.org/10.1115/ICONE29-90802
View Articletitled, SCM.SharedControls.Infrastructure.TitleDisplayModel?.Text
PDF
Topics: Very high temperature reactors
Extraction of Nd(III), Eu(III), Am(III) and Cm(III) With 6-Carboxylic Di(2-Ethylhexyl) Amide Pyridine
Chao Xu, Yu Du, Tingting Liu, Suliang Yang
ICONE 2022; V002T02A024https://doi.org/10.1115/ICONE29-90818
View Articletitled, SCM.SharedControls.Infrastructure.TitleDisplayModel?.Text
PDF
Topics: Atoms , Cycles , Design , Equilibrium (Physics) , Infrared spectra , Ion exchange , Mass transfer , Separation (Technology) , Spent nuclear fuels , Temperature
Prediction of the Operating Control Rod Position of the HTTR With Supervised Machine Learning
Hai Quan Ho, Satoru Nagasumi, Yosuke Shimazaki, Toshiaki Ishii, Kazuhiko Iigaki, Minoru Goto, Irwan Liapto Simanullang, Nozomu Fujimoto, Etsuo Ishitsuka
ICONE 2022; V002T02A025https://doi.org/10.1115/ICONE29-90826
View Articletitled, SCM.SharedControls.Infrastructure.TitleDisplayModel?.Text
PDF
Topics: Machine learning , Safety
The Wear and General Corrosion Properties of Low-Temperature Plasma Nitrided 17-4PH Stainless Steel With a Work-Hardened Sublayer
Zhongli Han, Ping Lai, Wenhua Zhuang, Xianglong Guo, Lefu Zhang
ICONE 2022; V002T02A026https://doi.org/10.1115/ICONE29-90835
View Articletitled, SCM.SharedControls.Infrastructure.TitleDisplayModel?.Text
PDF
Topics: Corrosion , Low temperature , Nitriding , Plasmas (Ionized gases) , Stainless steel , Wear
Study on Selection Method of Shielding Nuclides in Nuclear Reactor Based on Non-Dominated Sorting
Rui Li, Shichang Liu
ICONE 2022; V002T02A027https://doi.org/10.1115/ICONE29-90902
View Articletitled, SCM.SharedControls.Infrastructure.TitleDisplayModel?.Text
PDF
Topics: Nuclear reactors , Nuclides , Radiation (Physics) , Neutrons , Cross section (Physics) , Monte Carlo methods , Photons , Absorption , Databases , Elastic scattering
Study and Development of Irradiation Test Device for Fuel Rods In Research Reactor
Wenbin Zhao, Junping Si, Liang Zhang, Sheng Sun, Wenhua Yang, Shuai Jin, Jin Lei, Hao Liu
ICONE 2022; V002T02A028https://doi.org/10.1115/ICONE29-90997
View Articletitled, SCM.SharedControls.Infrastructure.TitleDisplayModel?.Text
PDF
Topics: Fuel rods , Irradiation (Radiation exposure)
Numerical Simulation of Fuel Relocation at High Burnup With Discrete Element Method
Zehua Ma, Ren Liang, Zhikang Lin, Yong Ouyang, Xianghui Lu, Guanghui Su
ICONE 2022; V002T02A029https://doi.org/10.1115/ICONE29-91377
View Articletitled, SCM.SharedControls.Infrastructure.TitleDisplayModel?.Text
PDF
Topics: Accidents , Computer simulation , Coolants , Discrete element methods , Fuels
Development and Preliminary Verification of Multi-Group Cross Section Processing Code MAGIC for Fast Reactor Based on Continuous Point Cross Section
Bin Zhang, Xubo Ma, Kui Hu, Teng Zhang, Yuqin Huang, Xuan Ma
ICONE 2022; V002T02A030https://doi.org/10.1115/ICONE29-91396
View Articletitled, SCM.SharedControls.Infrastructure.TitleDisplayModel?.Text
PDF
Topics: Fast neutron reactors , Resonance
Development and Verification of Multigroup Cross Section Generation Module GroupXS in AXSP
Kui Hu, Xubo Ma, Xuan Ma, Chen Zhang, Guanqun Jia, Yixue Chen
ICONE 2022; V002T02A031https://doi.org/10.1115/ICONE29-91399
View Articletitled, SCM.SharedControls.Infrastructure.TitleDisplayModel?.Text
PDF
Topics: Approximation , Cross section (Physics) , Errors , Intellectual property , Neutrons , Nuclear reactors , Nuclides , Physics
Design and Investigation of Liquid Lead-Bismuth Test Irradiation Loop in Research Reactor
Yuheng Xu, Juping Si, Liang Zhang, Sheng Sun, Hongwei Wu, Mengkang Lu
ICONE 2022; V002T02A032https://doi.org/10.1115/ICONE29-91405
View Articletitled, SCM.SharedControls.Infrastructure.TitleDisplayModel?.Text
PDF
Topics: Design , Irradiation (Radiation exposure)
Analysis of Double Heterogeneous Effect Under Double Dispersion of Fuel and Burnable Poison Particles
Anmin Yuan, Hongchun Wu, Yunzhao Li, Liangzhi Cao, Cong Wang, Chaofei Jiang, Shengzhi Yu, Qianglong Wang, Jinrong Qiu
ICONE 2022; V002T02A033https://doi.org/10.1115/ICONE29-91463
View Articletitled, SCM.SharedControls.Infrastructure.TitleDisplayModel?.Text
PDF
Topics: Fuels , Particulate matter
A Discrete-Ordinates Variational Nodal Method for Solving Multi-Dimensional Neutron Transport Equation With Unstructured Mesh
Qizheng Sun, Tengfei Zhang, Xiaojing Liu, Xiang Chai, Jinbiao Xiong
ICONE 2022; V002T02A034https://doi.org/10.1115/ICONE29-91525
View Articletitled, SCM.SharedControls.Infrastructure.TitleDisplayModel?.Text
PDF
Topics: Neutrons
Modelica Based Economic Analysis of Nuclear Fuel Cycle
Jie Liu, Xiang Wang
ICONE 2022; V002T02A035https://doi.org/10.1115/ICONE29-91600
View Articletitled, SCM.SharedControls.Infrastructure.TitleDisplayModel?.Text
PDF
Topics: Economic analysis , Economics , Nuclear fuel cycle
Numerical Simulation of Reactor Neutron Noise Based on Discrete Ordinate Finite Element Method
Baoxin Yuan, Xin Luo, Herong Zeng, Huan Huang, Jie Zheng, Wankui Yang, Songbao Zhang, Bin Zhong, Junxia Wei, Yangjun Ying
ICONE 2022; V002T02A036https://doi.org/10.1115/ICONE29-91726
View Articletitled, SCM.SharedControls.Infrastructure.TitleDisplayModel?.Text
PDF
Topics: Computer simulation , Finite element analysis , Finite element methods , Neutrons , Noise (Sound)
Neutronics comparative analysis of fuel assemblies using CSG and DAGMC methods
NingYan Sun, ShiChang Liu
ICONE 2022; V002T02A037https://doi.org/10.1115/ICONE29-91727
View Articletitled, SCM.SharedControls.Infrastructure.TitleDisplayModel?.Text
PDF
Topics: Fuels , Geometry , Computer-aided design , Modeling , Particulate matter , Monte Carlo methods
Development and Validation of a New Gas Conductance Model
Shengzhi Yang, Xiaoyan Wei, Yanan Zhu
ICONE 2022; V002T02A038https://doi.org/10.1115/ICONE29-91758
View Articletitled, SCM.SharedControls.Infrastructure.TitleDisplayModel?.Text
PDF
Topics: Electrical conductance , Temperature
Study on the Effect of Random Distribution of the Fuel in Dissolver
Miao Yu, Xuan Yi, Zeng Shao, Haifeng Yang
ICONE 2022; V002T02A039https://doi.org/10.1115/ICONE29-91800
View Articletitled, SCM.SharedControls.Infrastructure.TitleDisplayModel?.Text
PDF
Topics: Fuels , Particulate matter , Safety
Numerical Simulation Analysis of Silicon Carbide Whiskers Doped Uranium Dioxide Composite Fuel for High Thermal Conductivity
Linyuan Lu, LiHua Guo, Yajuan Zhong, Feng Zhang, Jun Lin
ICONE 2022; V002T02A040https://doi.org/10.1115/ICONE29-91804
View Articletitled, SCM.SharedControls.Infrastructure.TitleDisplayModel?.Text
PDF
Topics: Composite materials , Computer simulation , Fuels , Silicon , Temperature distribution , Thermal conductivity , Thermal resistance , Uranium , Finite element methods , Accidents
Multiphysics Thermo-Mechanical Behavior Modeling for Annular Uranium-Plutonium Mixed Oxide Fuels in a Lead-Cooled Fast Reactor
Yutai Cai, Wenzhong Zhou, Long Gu
ICONE 2022; V002T02A041https://doi.org/10.1115/ICONE29-91817
View Articletitled, SCM.SharedControls.Infrastructure.TitleDisplayModel?.Text
PDF
Topics: Fast neutron reactors , Fuels , Modeling , Thermomechanics , Uranium
Drop Analyses and Verification of the Spent Nuclear Fuel Transportation Cask Under Hypothetical Accident Conditions
Guangdong Liu, Weiliang Wu, He Zhu, Qingjun Ma, Qipeng Li
ICONE 2022; V002T02A042https://doi.org/10.1115/ICONE29-91927
View Articletitled, SCM.SharedControls.Infrastructure.TitleDisplayModel?.Text
PDF
Topics: Accidents , Spent nuclear fuels , Stress , Transportation systems
A Detailed Model to Predict Mechanical Characteristics of Fuel Assembly
Jingjing Zhao, Shiyin Xu, Wenan Pan, Jingya Sun, Yuxi Du
ICONE 2022; V002T02A043https://doi.org/10.1115/ICONE29-91931
View Articletitled, SCM.SharedControls.Infrastructure.TitleDisplayModel?.Text
PDF
Topics: Fuels , Manufacturing , Mechanical properties
The Study of Coupled Fuel Performance Analysis and Neutronics With COMSOL and RMC
Zhenhai Liu, Feipeng Qi, Yi Zhou, Quan Li, Ping Chen, Hao Chen, Chao Ma, Bo Zhao, Chenxi Li
ICONE 2022; V002T02A044https://doi.org/10.1115/ICONE29-92046
View Articletitled, SCM.SharedControls.Infrastructure.TitleDisplayModel?.Text
PDF
Topics: Fuels
Development and Application of High Temperature and Radiation Protection Equipment for Spent Fuel Dry Storage System
Cheng Cheng, Wei Yuanyuan, Pan Yongjie, Ge Yongjun, Wei Zhiguo, Zhou Zhihui, Li Zengfen
ICONE 2022; V002T02A045https://doi.org/10.1115/ICONE29-92083
View Articletitled, SCM.SharedControls.Infrastructure.TitleDisplayModel?.Text
PDF
Topics: High temperature , Radiation (Physics) , Risk , Spent nuclear fuels , Storage
Development and Verification of Neutron and Photon Ultrafine Group Library for Fast Reactor Physical Calculation
Teng Zhang, Xubo Ma, Guanqun Jia, Xuan Ma, Bin Zhang, Kui Hu
ICONE 2022; V002T02A046https://doi.org/10.1115/ICONE29-92091
View Articletitled, SCM.SharedControls.Infrastructure.TitleDisplayModel?.Text
PDF
Topics: Fast neutron reactors , Neutrons , Photons
Development and Experiment on High Temperature and Radiation Resistance Concrete Material for Spent Fuel Dry Storage
Zhang Xueling, Cheng Cheng, Pan Yongjie, Wei Yuanyuan, Tang Qionghui, Li Zengfen, Yang Shouhai
ICONE 2022; V002T02A047https://doi.org/10.1115/ICONE29-92125
View Articletitled, SCM.SharedControls.Infrastructure.TitleDisplayModel?.Text
PDF
Topics: Concretes , Fibers , High temperature , Radiation (Physics) , Spent nuclear fuels , Steel , Storage , Tension
Molecular Dynamics Study on Thermal Conductivity of Unirradiated and Irradiated Symmetrical Tilt Grain Boundary 3C-SiC
Ziqi Cai, Qingmin Zhang, Zhuang Shao, Yuanming Li
ICONE 2022; V002T02A048https://doi.org/10.1115/ICONE29-92136
View Articletitled, SCM.SharedControls.Infrastructure.TitleDisplayModel?.Text
PDF
Topics: Cascades (Fluid dynamics) , Grain boundaries , Molecular dynamics , Symmetry (Physics) , Thermal conductivity
Study on UC Phase Control of UC Ceramic Microspheres Prepared by Sol-Gel Method
Feng Wen, Bolong Guo, Mingyang Li, Jiachen Wang, Fan Zhang, Wei Liu, Wenkai Ma, Zhihua Liu
ICONE 2022; V002T02A049https://doi.org/10.1115/ICONE29-92188
View Articletitled, SCM.SharedControls.Infrastructure.TitleDisplayModel?.Text
PDF
Topics: Ceramics , Sol-gel processing
Research Progress of Neutron Shielding Materials
Bing Chang, Saisai Li, Minghui Li, Ruoyu Chen
ICONE 2022; V002T02A050https://doi.org/10.1115/ICONE29-92210
View Articletitled, SCM.SharedControls.Infrastructure.TitleDisplayModel?.Text
PDF
Topics: Metals , Neutrons , Polymers
Thermal Experimental and Analysis of Vertical Spent Fuel Dry Storage Canister
Qionghui Tang, Mao-Yun Li, Cheng Cheng, En-Fei Xie
ICONE 2022; V002T02A051https://doi.org/10.1115/ICONE29-92217
View Articletitled, SCM.SharedControls.Infrastructure.TitleDisplayModel?.Text
PDF
Topics: Computational fluid dynamics , Spent nuclear fuels , Storage
Phase-Field Fracture Simulation of Dual-Cooled Annular Fuel Pellet
Wei Li
ICONE 2022; V002T02A052https://doi.org/10.1115/ICONE29-92230
View Articletitled, SCM.SharedControls.Infrastructure.TitleDisplayModel?.Text
PDF
Topics: Fracture (Process) , Fuels , Simulation
Investigation of Swelling Behaviors of U-10Zr Metallic Fuel in the Low Temperature Regime via a Combined Thermo-Mechanical and Rate Theory Analysis
Zhengyu Qian, Di Yun
ICONE 2022; V002T02A053https://doi.org/10.1115/ICONE29-92285
View Articletitled, SCM.SharedControls.Infrastructure.TitleDisplayModel?.Text
PDF
Topics: Fuels , Low temperature , Thermomechanics , Uranium , Zirconium
Effect of Contact Stress on Fretting Corrosion Behavior of Alloy 690 Tube Exposed to Simulated Secondary Water
Wenhua Zhuang, Zhongli Han, Xianglong Guo, Lefu Zhang
ICONE 2022; V002T02A054https://doi.org/10.1115/ICONE29-92395
View Articletitled, SCM.SharedControls.Infrastructure.TitleDisplayModel?.Text
PDF
Topics: Alloys , Corrosion , Stress , Water , Wear
Application of Stiffness Confinement Method on Pin Resolved Variational Nodal Method and Its Implementation to C5G7-TD Benchmark Problem
Wei Xiao, Tengfei Zhang, Xiaojing Liu, Donghao He, Qingquan Pan
ICONE 2022; V002T02A055https://doi.org/10.1115/ICONE29-92399
View Articletitled, SCM.SharedControls.Infrastructure.TitleDisplayModel?.Text
PDF
Topics: Stiffness
Analysis of Trace Components in Neon by Gas Chromatography
Li-ling Yang, Qin Zhan
ICONE 2022; V002T02A056https://doi.org/10.1115/ICONE29-92413
View Articletitled, SCM.SharedControls.Infrastructure.TitleDisplayModel?.Text
PDF
Topics: Fusion reactors , Gas chromatography , Measurement systems
Corrosion Behavior of a Novel Alumina Forming Austenitic Steel Exposed to Supercritical Water
Dayun Sun, Yang Gao, Shuo Cong, Xianglong Guo
ICONE 2022; V002T02A057https://doi.org/10.1115/ICONE29-92471
View Articletitled, SCM.SharedControls.Infrastructure.TitleDisplayModel?.Text
PDF
Topics: Corrosion , Steel , Water
The Study of a New Efficient Monte Carlo Method for Deep-Penetration Transport
Tao Zhang, Zhihong Liu, Ding She, Jing Zhao
ICONE 2022; V002T02A058https://doi.org/10.1115/ICONE29-92621
View Articletitled, SCM.SharedControls.Infrastructure.TitleDisplayModel?.Text
PDF
Topics: Monte Carlo methods
Structural Design and Dynamic Analysis of the Heat Exchanger Used in Nuclear Fuel Test Loop
Huang Gang, Sun Sheng, Pan Liangming, Si Junping
ICONE 2022; V002T02A059https://doi.org/10.1115/ICONE29-92625
View Articletitled, SCM.SharedControls.Infrastructure.TitleDisplayModel?.Text
PDF
Topics: Design , Dynamic analysis , Heat exchangers , Nuclear fuels , Stress , Structural design
Numerical Study of the Effect of δ-Ferrite on Crack-Tip Mechanical Field
Yule Wu, Lefu Zhang
ICONE 2022; V002T02A060https://doi.org/10.1115/ICONE29-92656
View Articletitled, SCM.SharedControls.Infrastructure.TitleDisplayModel?.Text
PDF
Topics: Ferrites (Magnetic materials) , Fracture (Materials) , Stress , Cracking (Materials) , Fracture (Process) , Embrittlement , Finite element analysis , Finite element methods , Finite element model , High temperature
Fission Gas Release Grain Boundary Network Percolation Mechanistic Studies in Oxide Fuels Based on COMSOL Multiphysics Framework
Jingyu Guo, Wenzhong Zhou
ICONE 2022; V002T02A061https://doi.org/10.1115/ICONE29-92732
View Articletitled, SCM.SharedControls.Infrastructure.TitleDisplayModel?.Text
PDF
Topics: Fuels , Grain boundaries , Nuclear fission , Percolation theory
Research on Establishing Efficient Scheduling System of Spent Fuel From Chinese Nuclear Power Plants
Jiqiang Su, Qun Liu, Honglin Zhang, Lei Shi, Hongjun Liu, Yanrui Li, Jian Hu
ICONE 2022; V002T02A062https://doi.org/10.1115/ICONE29-92757
View Articletitled, SCM.SharedControls.Infrastructure.TitleDisplayModel?.Text
PDF
Topics: Nuclear power stations , Spent nuclear fuels , Transportation systems
A Method to Evaluate Defect Size of Failed Fuel Rods in CGN 1000MWe PWRs
Pengtao Fu, Zhijun Li
ICONE 2022; V002T02A063https://doi.org/10.1115/ICONE29-92788
View Articletitled, SCM.SharedControls.Infrastructure.TitleDisplayModel?.Text
PDF
Topics: Failure , Fuel rods , Fuels , Nuclear fission , Pressurized water reactors , Cladding systems (Building) , Rods , Irradiation (Radiation exposure)
Key Impact Factors Analysis of Fuel Rod End Plug Welding Based on QFD
Yinghong Li, Zhipeng Lv, Changzheng Li, Yuyu Lin, Shaofang Lin, Zhiyi Cai, Yongjun Deng, Lihong Nie
ICONE 2022; V002T02A064https://doi.org/10.1115/ICONE29-92803
View Articletitled, SCM.SharedControls.Infrastructure.TitleDisplayModel?.Text
PDF
Topics: Fuel rods , Fuels , Reliability , Welding
Interpretation and Analysis of Design Idea of the Spent Fuel Transport Ship
Gui Zhong, Zhang Hui, Wang Wei, Yuan Yueyan, Liu Chao, Li Xiaoqing
ICONE 2022; V002T02A065https://doi.org/10.1115/ICONE29-92809
View Articletitled, SCM.SharedControls.Infrastructure.TitleDisplayModel?.Text
PDF
Topics: Design , Safety , Ships , Spent nuclear fuels
Effects of Stoichiometry and High-Temperature Annealing on Zirconium Carbide Coating Layer in TRISO Particles
Xinyu Cheng, Rongzheng Liu, Bing Liu, Xu Yang, Malin Liu, Jiaxing Chang, Youlin Shao
ICONE 2022; V002T02A066https://doi.org/10.1115/ICONE29-92858
View Articletitled, SCM.SharedControls.Infrastructure.TitleDisplayModel?.Text
PDF
Topics: Annealing , Coatings , Fuels , High temperature , Particulate matter , Stoichiometry , Very high temperature reactors , Zirconium
Study on Risk of Nuclear Spent Fuel Marine Transportation
Liu Yiqing, Wang Wei, Zhao Xiaodong, Gui Zhong, Chen Jiangtao
ICONE 2022; V002T02A067https://doi.org/10.1115/ICONE29-92870
View Articletitled, SCM.SharedControls.Infrastructure.TitleDisplayModel?.Text
PDF
Topics: Marine transportation , Risk , Risk analysis , Spent nuclear fuels
Preliminary Sensitivity and Uncertainty Analysis of Accident Tolerant Fuel in SMR
Yuxuan Liang, Xiang Wang
ICONE 2022; V002T02A068https://doi.org/10.1115/ICONE29-92887
View Articletitled, SCM.SharedControls.Infrastructure.TitleDisplayModel?.Text
PDF
Topics: Accidents , Fuels , Sensitivity analysis , Uncertainty analysis
Study on the Policy and Legislative System of Spent Nuclear Fuel Management in Different Developed Countries
Lei Shi, Chao Chen, Hongjun Liu, Jiqiang Su, Honglin Zhang, Qun Liu, Yanrui Li, Jian Hu
ICONE 2022; V002T02A069https://doi.org/10.1115/ICONE29-92948
View Articletitled, SCM.SharedControls.Infrastructure.TitleDisplayModel?.Text
PDF
Topics: Spent nuclear fuels
Summary of the History of Improvement and Optimization of Fuel Management Strategies for Two 1000 MWe PWR Units
Zhou Xiaoling, Xu Zhixian, Zhao Bingquan, Li Wen, Zhong Shengdong, Gao Jinghui
ICONE 2022; V002T02A070https://doi.org/10.1115/ICONE29-92954
View Articletitled, SCM.SharedControls.Infrastructure.TitleDisplayModel?.Text
PDF
Topics: Cycles , Fuel management , Fuels , Leakage , Optimization , Pressurized water reactors
Study on Separation of Palladium From High Level Liquid Waste by Potassium Manganese Ferrocyanide
Tianming Qi, Hongji Sang, Cong Mao, Yueying Wen, Jipu Hu, Yan Wu
ICONE 2022; V002T02A071https://doi.org/10.1115/ICONE29-92971
View Articletitled, SCM.SharedControls.Infrastructure.TitleDisplayModel?.Text
PDF
Topics: Palladium , Potassium , Separation (Technology)
Improvements on Fuel Failures Diagnosis Method for Pressurized Water Reactor Nuclear Power Plant Based on Radioactive Activities Inside the Waste Gas Treatment System
Weifeng Lyu, Runchun Guo, Wenwang Ran, Yaoyi Gao, Jun Xiong
ICONE 2022; V002T02A072https://doi.org/10.1115/ICONE29-92996
View Articletitled, SCM.SharedControls.Infrastructure.TitleDisplayModel?.Text
PDF
Topics: Failure , Fuels , Nuclear power stations , Pressurized water reactors
A Digital Proof of Concept (POC) for Simulating the Coupled Phenomena Between Neutronics, Structural and Fluid Dynamics in a Reactor Core
Jie Liu, Chunyu Zhang, Zhihao Zheng, Jiesheng Min
ICONE 2022; V002T02A073https://doi.org/10.1115/ICONE29-93008
View Articletitled, SCM.SharedControls.Infrastructure.TitleDisplayModel?.Text
PDF
Topics: Fluid dynamics , Physics , Simulation , Computational fluid dynamics , Structural analysis , American Petroleum Institute , Computation , Computer simulation , Computer software , Computer-aided engineering
Analysis Method to Predict Grid-to-Rod Fretting Wear of Fuel Rod in Pressurized Water Reactors
Libing Zhu, Shufeng Zhao, Jingya Sun, Shiyin Xu, Fujun Gan, Sirui Li
ICONE 2022; V002T02A074https://doi.org/10.1115/ICONE29-93076
View Articletitled, SCM.SharedControls.Infrastructure.TitleDisplayModel?.Text
PDF
Topics: Fuel rods , Pressurized water reactors , Wear
Implementation and Verification of the DAGMC Module in Monte Carlo Code RMC
Pengfei Shen, Jingang Liang, Shichang Liu, Kan Wang
ICONE 2022; V002T02A075https://doi.org/10.1115/ICONE29-93103
View Articletitled, SCM.SharedControls.Infrastructure.TitleDisplayModel?.Text
PDF
Topics: Computer-aided design , Engineering simulation , Geometry , Nuclear reactors , Particulate matter , Physics , Simulation , Transport processes , Weight (Mass)
Patent Perspective on the Development of Metal Nuclear Fuel Technology
Haoliang Zhong, Yu Si, Xiaofei Chen, Yading Zhang, Ran Su
ICONE 2022; V002T02A076https://doi.org/10.1115/ICONE29-93138
View Articletitled, SCM.SharedControls.Infrastructure.TitleDisplayModel?.Text
PDF
Topics: Metals , Nuclear fuels , Patents
Study on Synthesis of the Organophosphorus Functionalized MCM-41 And its Adsorption Property for Dy(III)
Cong Mao, Hongji Sang, Jiawei Zheng, Yan Wu
ICONE 2022; V002T02A077https://doi.org/10.1115/ICONE29-93196
View Articletitled, SCM.SharedControls.Infrastructure.TitleDisplayModel?.Text
PDF
Topics: Composite materials , Fittings , Metals , Sewage , Temperature , Water , Zirconium
PWR Spent Fuel Dry Storage Loading Pattern and Safety Evaluation
Li Wen, Gao Jinghui, Li Gang, Zhong Shengdong, Xu Jin, Zhao Bingquan
ICONE 2022; V002T02A078https://doi.org/10.1115/ICONE29-93351
View Articletitled, SCM.SharedControls.Infrastructure.TitleDisplayModel?.Text
PDF
Topics: Pressurized water reactors , Safety , Spent nuclear fuels , Storage
Feasibility Study on Power Ramp Test Under Atmospheric Pressure and Ordinary Temperature
Xiangyu Wei, Wenhua Zhang, Yingchun Zhao
ICONE 2022; V002T02A079https://doi.org/10.1115/ICONE29-93417
View Articletitled, SCM.SharedControls.Infrastructure.TitleDisplayModel?.Text
PDF
Topics: Atmospheric pressure , Fuels , Ropes , Temperature , Cladding systems (Building) , Stress , Fuel rods , Irradiation (Radiation exposure) , Pressure , Sensitivity analysis
Efficient Dynamic Monte Carlo Simulation in Multi-Physics Coupling Calculation
Danhua ShangGuan, Weihua Yan, Junxia Wei, Zhiming Gao, Yibing Chen, Zhicheng Ji
ICONE 2022; V002T02A080https://doi.org/10.1115/ICONE29-93460
View Articletitled, SCM.SharedControls.Infrastructure.TitleDisplayModel?.Text
PDF
Topics: Monte Carlo methods , Physics , Simulation
Research on the Correlations of Fission Source Distribution in the Monte Carlo Algorithm Using Mathematical Tools
Pengfei Shen, Shihang Jiang, Yingzhe Hu, Kan Wang
ICONE 2022; V002T02A081https://doi.org/10.1115/ICONE29-93476
View Articletitled, SCM.SharedControls.Infrastructure.TitleDisplayModel?.Text
PDF
Topics: Algorithms , Cycles , Nuclear fission
Calculation of Detector Response Rate Based on BEAVRS Benchmark Using PWR-Core Analysis Code CORAL
Wen Yang, Baolin Liu, Shiwei Yao, Fei Chao, Xing Li, Jinrong Qiu
ICONE 2022; V002T02A082https://doi.org/10.1115/ICONE29-93495
View Articletitled, SCM.SharedControls.Infrastructure.TitleDisplayModel?.Text
PDF
Topics: Pressurized water reactors , Sensors
High Temperature Oxidation Kinetics of Zr-Sn-Nb Alloy and the Effect of Its Oxide Film Growth On Corrosion Resistance
Wanqian Zhao
ICONE 2022; V002T02A083https://doi.org/10.1115/ICONE29-93520
View Articletitled, SCM.SharedControls.Infrastructure.TitleDisplayModel?.Text
PDF
Topics: Alloys , Corrosion resistance , High temperature , Oxidation , Tin , Zirconium , Zirconium alloys
Summary of Geometric Parameters and Their Effects on Performance of U-10Mo Fuel Plates
Hakan Ozaltun, Hee Seok Roh, Walid Mohamed
ICONE 2022; V002T02A084https://doi.org/10.1115/ICONE29-93700
View Articletitled, SCM.SharedControls.Infrastructure.TitleDisplayModel?.Text
PDF
Topics: Fuels , Plates (structures)
Study on Fatigue Properties of Hydrided CZ2 Alloy
Jieming Huang, Changyuan Gao, Liutao Chen, Xu Wang, Jun Tan
ICONE 2022; V002T02A085https://doi.org/10.1115/ICONE29-93763
View Articletitled, SCM.SharedControls.Infrastructure.TitleDisplayModel?.Text
PDF
Topics: Alloys , Fatigue , Fatigue properties
Microstructual and Micro-Chemical Analysis of Zr Cladding Alloys on Corrosion and Creep Properties
Qing Yang Lv, Libin Zhang, Minli Chen, Changyuan Gao, Yang Xu, Liutao Chen, Jun Tan
ICONE 2022; V002T02A086https://doi.org/10.1115/ICONE29-93770
View Articletitled, SCM.SharedControls.Infrastructure.TitleDisplayModel?.Text
PDF
Topics: Alloys , Annealing , Cladding systems (Building) , Corrosion , Creep , Tin , Zirconium
Oxidation Behaviour of CZ Alloys Under High Temperature Steam
Minli Chen, Changyuan Gao, Guoliang Zhang, Lin Shi, Liutao Chen, Jun Tan
ICONE 2022; V002T02A087https://doi.org/10.1115/ICONE29-93795
View Articletitled, SCM.SharedControls.Infrastructure.TitleDisplayModel?.Text
PDF
Topics: Alloys , High temperature steam , Oxidation , Steam , Zirconium alloys
Study of Pre-Oxidization Law and Fretting Wear Resistance of CZ2 Alloy Cladding
Guocheng Sun, Shi Lin, Xu Wang, Liutao Chen
ICONE 2022; V002T02A088https://doi.org/10.1115/ICONE29-93804
View Articletitled, SCM.SharedControls.Infrastructure.TitleDisplayModel?.Text
PDF
Topics: Alloys , Cladding systems (Building) , Wear , Wear resistance
Study on Out-Pile Performance of CZ Zirconium Alloy Guide Tube
Changyuan Gao, Lin Shi, Guoliang Zhang, Yang Xu, Minli Chen, Liutao Chen, Jun Tan
ICONE 2022; V002T02A089https://doi.org/10.1115/ICONE29-93816
View Articletitled, SCM.SharedControls.Infrastructure.TitleDisplayModel?.Text
PDF
Topics: Corrosion , Creep , Zirconium alloys , Alloys , Zirconium , Corrosion resistance , Stress , Temperature , Mechanical testing , Particulate matter
Study on Water Chemistry and Temperature Adaptability of CZ Zirconium Alloy
Hansen Chen, Changyuan Gao, Liutao Chen, Xu Wang, Jun Tan
ICONE 2022; V002T02A090https://doi.org/10.1115/ICONE29-93820
View Articletitled, SCM.SharedControls.Infrastructure.TitleDisplayModel?.Text
PDF
Topics: Temperature , Water chemistry , Zirconium alloys
Study of Iodine-Induced Stress Corrosion Cracking of CZ2 Alloy
Lin Shi, Changyuan Gao, Guoliang Zhang, Guocheng Sun, Xu Wang, Liutao Chen, Jun Tan
ICONE 2022; V002T02A091https://doi.org/10.1115/ICONE29-93835
View Articletitled, SCM.SharedControls.Infrastructure.TitleDisplayModel?.Text
PDF
Topics: Alloys , Fracture (Materials) , Fracture (Process) , Stress corrosion cracking
The Research of Corrosion Resistance of CZ2 Zirconium Alloy Welding Specimens
Yang Xu, Liu-Tao Chen, Chang-Yuan Gao, Jun Tan, Lin Shi
ICONE 2022; V002T02A092https://doi.org/10.1115/ICONE29-93838
View Articletitled, SCM.SharedControls.Infrastructure.TitleDisplayModel?.Text
PDF
Topics: Corrosion , Corrosion resistance , Weight (Mass) , Welding , Zirconium alloys
Study on Properties of Aging and Immersion in Boric Acid Water of PEEK Insulation Material
Jing An, Shan Jin, Li-Qin Zhang, Hao Wu
ICONE 2022; V002T02A093https://doi.org/10.1115/ICONE29-93867
View Articletitled, SCM.SharedControls.Infrastructure.TitleDisplayModel?.Text
PDF
Topics: Insulation , Mechanical properties , Water
Potential Crud Related Margin Gains With Chromium Coated Zirconium Cladding
William A. Byers, Guoqiang Wang
ICONE 2022; V002T02A094https://doi.org/10.1115/ICONE29-94477
View Articletitled, SCM.SharedControls.Infrastructure.TitleDisplayModel?.Text
PDF
Topics: Cladding systems (Building) , Zirconium , Corrosion , Coating processes , Coatings , Fuels , Pressurized water reactors , Accidents , Boiling , Boron
Applying Machine Learning to Improve BOA Analysis of CIPS/CILC
Jun Liao, Alexander Mace, Guoqiang Wang, Jesse S. Fisher
ICONE 2022; V002T02A095https://doi.org/10.1115/ICONE29-94480
View Articletitled, SCM.SharedControls.Infrastructure.TitleDisplayModel?.Text
PDF
Topics: Machine learning , Boron , Corrosion , Fuels , Nuclear power stations , Algorithms , Calibration , Chemistry , Cladding systems (Building) , Computers
All Years

ASME Journals

ASME Conference Proceedings

ASME eBooks

Resources

Opportunities

  • Crossref Logo
  • Crossref Open Funder Registry Logo
  • Crossref Open Cited-By Logo
  • Crossref Crossmark Logo
  • Crossref Similarity Check Logo
  • Chorus Logo
  • Counter Logo
  • Cope Logo
  • STM Logo
Copyright © 2025 The American Society of Mechanical Engineers
This Feature Is Available To Subscribers Only

or Create an Account

Close Modal
Close Modal