1-20 of 8993
Save search
Follow your search
Access your saved searches in your account
Would you like to receive an alert when new items match your search?
Close Modal
Sort by
Proceedings Papers

Research on Qualification Requirements for Electrical and Instrumentation Equipment Based on Safety Classification

Available to Purchase

Qian Sun, Jiahao Liu
Proc. ASME. ICONE31, Volume 9: Advanced Methods of Manufacturing for Nuclear Reactors and Components; Severe Accidents and Mitigation Strategies for Beyond Design Basis Events, V009T10A012, August 4–8, 2024
Publisher: American Society of Mechanical Engineers
Paper No: ICONE31-136504
https://doi.org/10.1115/ICONE31-136504
View Paper titled, Research on Qualification Requirements for Electrical and Instrumentation Equipment Based on Safety Classification
Open the PDF for Research on Qualification Requirements for Electrical and Instrumentation Equipment Based on Safety Classification in another window
Topics: Design, Equipment qualification, Instrumentation, Safety
Proceedings Papers

Analysis of the Effect of Random Bowing of the Fuel Pin on the Power Distribution in the Fuel Assembly

Available to Purchase

Jiří Závorka, Martin Lovecký, Radek Škoda, Petra Monhartová
Proc. ASME. ICONE31, Volume 2: Nuclear Fuel and Material, Reactor Physics and Transport Theory, and Fuel Cycle Technology, V002T02A059, August 4–8, 2024
Publisher: American Society of Mechanical Engineers
Paper No: ICONE31-136287
https://doi.org/10.1115/ICONE31-136287
View Paper titled, Analysis of the Effect of Random Bowing of the Fuel Pin on the Power Distribution in the Fuel Assembly
Open the PDF for Analysis of the Effect of Random Bowing of the Fuel Pin on the Power Distribution in the Fuel Assembly in another window
Topics: Fuels, Manufacturing
Proceedings Papers

Analysis on Permeation Leakage Through Rubber Sealing Ring for Radioactive Material Transport Packages

Available to Purchase

Pengyi Wang, Dajie Zhuang, Hongchao Sun, Lei Chen
Proc. ASME. ICONE31, Volume 2: Nuclear Fuel and Material, Reactor Physics and Transport Theory, and Fuel Cycle Technology, V002T02A058, August 4–8, 2024
Publisher: American Society of Mechanical Engineers
Paper No: ICONE31-136263
https://doi.org/10.1115/ICONE31-136263
View Paper titled, Analysis on Permeation Leakage Through Rubber Sealing Ring for Radioactive Material Transport Packages
Open the PDF for Analysis on Permeation Leakage Through Rubber Sealing Ring for Radioactive Material Transport Packages in another window
Topics: Helium, Leakage, Radioactive substances, Rubber, Sealing (Process), Testing, Transport packages
Proceedings Papers

Investigation on Applicability of Dynamic Mode Decomposition in Burnup Analysis

Available to Purchase

Pengchao Xue, Qian Zhang, Qiang Zhao, Yunfei Zhang
Proc. ASME. ICONE31, Volume 2: Nuclear Fuel and Material, Reactor Physics and Transport Theory, and Fuel Cycle Technology, V002T02A039, August 4–8, 2024
Publisher: American Society of Mechanical Engineers
Paper No: ICONE31-135535
https://doi.org/10.1115/ICONE31-135535
View Paper titled, Investigation on Applicability of Dynamic Mode Decomposition in Burnup Analysis
Open the PDF for Investigation on Applicability of Dynamic Mode Decomposition in Burnup Analysis in another window
Topics: Algorithms, Density, Dynamics (Mechanics), Fuels, Manufacturing, Neutrons, Nuclides, Spatiotemporal phenomena
Proceedings Papers

Bamboo-Frame: An Automatic Modeling Tool for the Two-Step Reactor Core Physics Analysis

Available to Purchase

Yuancheng Zhou, Yunzhao Li, Yisong Li, Yilin Liang, Hengrui Zhang, Shilong Zhou, Weiguo Wang, Yuxiang Ou
Proc. ASME. ICONE31, Volume 2: Nuclear Fuel and Material, Reactor Physics and Transport Theory, and Fuel Cycle Technology, V002T02A038, August 4–8, 2024
Publisher: American Society of Mechanical Engineers
Paper No: ICONE31-135358
https://doi.org/10.1115/ICONE31-135358
View Paper titled, Bamboo-Frame: An Automatic Modeling Tool for the Two-Step Reactor Core Physics Analysis
Open the PDF for Bamboo-Frame: An Automatic Modeling Tool for the Two-Step Reactor Core Physics Analysis in another window
Topics: Modeling, Physics, Pressurized water reactors
Proceedings Papers

Effect of Heat Treatment on Microstructure Characteristics of Hot Worked Zr-2.5Nb Alloy Tubes

Available to Purchase

Jianming Yin, Bo Gao, Baifeng Luan, Yan Zhang
Proc. ASME. ICONE31, Volume 2: Nuclear Fuel and Material, Reactor Physics and Transport Theory, and Fuel Cycle Technology, V002T02A021, August 4–8, 2024
Publisher: American Society of Mechanical Engineers
Paper No: ICONE31-134410
https://doi.org/10.1115/ICONE31-134410
View Paper titled, Effect of Heat Treatment on Microstructure Characteristics of Hot Worked Zr-2.5Nb Alloy Tubes
Open the PDF for Effect of Heat Treatment on Microstructure Characteristics of Hot Worked Zr-2.5Nb Alloy Tubes in another window
Topics: Alloys, Heat treating (Metalworking), Zirconium
Proceedings Papers

Further Study of China’s Strategy for Closed Nuclear Fuel Cycle Development Against the Carbon Neutrality Target

Available to Purchase

Ding Chen, Lei Shi, Jiqiang Su, Yan An, Yihan Wang
Proc. ASME. ICONE31, Volume 2: Nuclear Fuel and Material, Reactor Physics and Transport Theory, and Fuel Cycle Technology, V002T02A014, August 4–8, 2024
Publisher: American Society of Mechanical Engineers
Paper No: ICONE31-133248
https://doi.org/10.1115/ICONE31-133248
View Paper titled, Further Study of China’s Strategy for Closed Nuclear Fuel Cycle Development Against the Carbon Neutrality Target
Open the PDF for Further Study of China’s Strategy for Closed Nuclear Fuel Cycle Development Against the Carbon Neutrality Target in another window
Topics: Carbon neutrality, Nuclear fuel cycle
Proceedings Papers

Further Investigation of Neutron Noise Under the Condition of Fuel Failure Based on Frequency Domain Finite Element Method

Available to Purchase

Baoxin Yuan, Huiyi Lv, Herong Zeng, Jie Zheng, Zihan Chen, Huan Huang, Songbao Zhang, Dazhi Qian
Proc. ASME. ICONE31, Volume 2: Nuclear Fuel and Material, Reactor Physics and Transport Theory, and Fuel Cycle Technology, V002T02A005, August 4–8, 2024
Publisher: American Society of Mechanical Engineers
Paper No: ICONE31-132052
https://doi.org/10.1115/ICONE31-132052
View Paper titled, Further Investigation of Neutron Noise Under the Condition of Fuel Failure Based on Frequency Domain Finite Element Method
Open the PDF for Further Investigation of Neutron Noise Under the Condition of Fuel Failure Based on Frequency Domain Finite Element Method in another window
Topics: Damage, Failure, Finite element methods, Fuels, Neutrons, Noise (Sound)
Proceedings Papers

TRISO Particle Behavior Analyses of an HTR-10 Type Reactor Employing the OTTO Operation Scheme

Available to Purchase

Junxiao Zhang, Songyang Liu, Junhao Xie, Tian Zhang
Proc. ASME. ICONE31, Volume 2: Nuclear Fuel and Material, Reactor Physics and Transport Theory, and Fuel Cycle Technology, V002T02A053, August 4–8, 2024
Publisher: American Society of Mechanical Engineers
Paper No: ICONE31-136107
https://doi.org/10.1115/ICONE31-136107
View Paper titled, TRISO Particle Behavior Analyses of an HTR-10 Type Reactor Employing the OTTO Operation Scheme
Open the PDF for TRISO Particle Behavior Analyses of an HTR-10 Type Reactor Employing the OTTO Operation Scheme in another window
Topics: Fuels, High temperature, Particulate matter, Nuclear fission, Temperature, Very high temperature reactors, Diffusion (Physics), Failure, Flow (Dynamics), Safety
Proceedings Papers

Study on the Characteristics of Nuclear Fuel Industry

Available to Purchase

Lei Shi, Yihan Wang, Hongjun Liu, Honglin Zhang
Proc. ASME. ICONE31, Volume 2: Nuclear Fuel and Material, Reactor Physics and Transport Theory, and Fuel Cycle Technology, V002T02A052, August 4–8, 2024
Publisher: American Society of Mechanical Engineers
Paper No: ICONE31-136048
https://doi.org/10.1115/ICONE31-136048
View Paper titled, Study on the Characteristics of Nuclear Fuel Industry
Open the PDF for Study on the Characteristics of Nuclear Fuel Industry in another window
Topics: Nuclear fuels
Proceedings Papers

Three-Dimensional Refined Burnup Calculation of Helical-Cruciform Nuclear Fuel

Available to Purchase

Duan Qianni, Li Wei, Wu Junmei
Proc. ASME. ICONE31, Volume 2: Nuclear Fuel and Material, Reactor Physics and Transport Theory, and Fuel Cycle Technology, V002T02A035, August 4–8, 2024
Publisher: American Society of Mechanical Engineers
Paper No: ICONE31-135085
https://doi.org/10.1115/ICONE31-135085
View Paper titled, Three-Dimensional Refined Burnup Calculation of Helical-Cruciform Nuclear Fuel
Open the PDF for Three-Dimensional Refined Burnup Calculation of Helical-Cruciform Nuclear Fuel in another window
Topics: High cycle fatigue, Nuclear fuels, Neutrons, Physics, Power density, Fuels, Geometry, Innovation, Thermal hydraulics, Uranium
Proceedings Papers

A Review of the Performance Analysis of Plate Type Fuel Elements in High-Flux Reactors

Available to Purchase

Yue Song, Heng Xie, Meng Lv
Proc. ASME. ICONE31, Volume 2: Nuclear Fuel and Material, Reactor Physics and Transport Theory, and Fuel Cycle Technology, V002T02A034, August 4–8, 2024
Publisher: American Society of Mechanical Engineers
Paper No: ICONE31-135005
https://doi.org/10.1115/ICONE31-135005
View Paper titled, A Review of the Performance Analysis of Plate Type Fuel Elements in High-Flux Reactors
Open the PDF for A Review of the Performance Analysis of Plate Type Fuel Elements in High-Flux Reactors in another window
Topics: Corrosion, Fuels, Irradiation (Radiation exposure), Safety, Temperature effects
Proceedings Papers

High-Fidelity Depletion-Pebble-Flow Coupling Simulation of Pebble Bed Reactor HTR-PM

Available to Purchase

Ruihan Li, Jingang Liang, Ding She, Weijian Zhang
Proc. ASME. ICONE31, Volume 2: Nuclear Fuel and Material, Reactor Physics and Transport Theory, and Fuel Cycle Technology, V002T02A024, August 4–8, 2024
Publisher: American Society of Mechanical Engineers
Paper No: ICONE31-134641
https://doi.org/10.1115/ICONE31-134641
View Paper titled, High-Fidelity Depletion-Pebble-Flow Coupling Simulation of Pebble Bed Reactor HTR-PM
Open the PDF for High-Fidelity Depletion-Pebble-Flow Coupling Simulation of Pebble Bed Reactor HTR-PM in another window
Topics: Discrete element methods, Flow (Dynamics), Simulation
Proceedings Papers

Multi-Mesh Approach for Geometry-Independent Neutronic/Thermal-Hydraulics Coupling Analyses Using RMC and Ansys Fluent

Available to Purchase

Xingyu Zhao, Guodong Liu, Shanfang Huang, Qiaoyan Chen, Hao Luo, Ying He, Junren Hou, Kan Wang
Proc. ASME. ICONE31, Volume 2: Nuclear Fuel and Material, Reactor Physics and Transport Theory, and Fuel Cycle Technology, V002T02A015, August 4–8, 2024
Publisher: American Society of Mechanical Engineers
Paper No: ICONE31-133607
https://doi.org/10.1115/ICONE31-133607
View Paper titled, Multi-Mesh Approach for Geometry-Independent Neutronic/Thermal-Hydraulics Coupling Analyses Using RMC and Ansys Fluent
Open the PDF for Multi-Mesh Approach for Geometry-Independent Neutronic/Thermal-Hydraulics Coupling Analyses Using RMC and Ansys Fluent in another window
Topics: Computational fluid dynamics, Geometry, Thermal hydraulics
Proceedings Papers

Evaluation of Expansion Reactivity Based on Reactivity Coefficient for Sodium-Cooled Fast Reactor

Available to Purchase

Satoshi Takeda, Takanori Kitada, Eiji Hoashi, Takafumi Okita
Proc. ASME. ICONE31, Volume 2: Nuclear Fuel and Material, Reactor Physics and Transport Theory, and Fuel Cycle Technology, V002T02A006, August 4–8, 2024
Publisher: American Society of Mechanical Engineers
Paper No: ICONE31-132277
https://doi.org/10.1115/ICONE31-132277
View Paper titled, Evaluation of Expansion Reactivity Based on Reactivity Coefficient for Sodium-Cooled Fast Reactor
Open the PDF for Evaluation of Expansion Reactivity Based on Reactivity Coefficient for Sodium-Cooled Fast Reactor in another window
Topics: Sodium fast reactors
Proceedings Papers

Fast Solution of Schrödinger Equation Based on Complex One-Dimensional Potential Wells

Available to Purchase

Zihao Liu, Xiang Wang
Proc. ASME. ICONE31, Volume 2: Nuclear Fuel and Material, Reactor Physics and Transport Theory, and Fuel Cycle Technology, V002T02A067, August 4–8, 2024
Publisher: American Society of Mechanical Engineers
Paper No: ICONE31-137072
https://doi.org/10.1115/ICONE31-137072
View Paper titled, Fast Solution of Schrödinger Equation Based on Complex One-Dimensional Potential Wells
Open the PDF for Fast Solution of Schrödinger Equation Based on Complex One-Dimensional Potential Wells in another window
Topics: Schrödinger equation, Wells
Proceedings Papers

Adsorption and Diffusion of Silver on SiC(111) and ZrC(111) Surfaces: A First Principles Study

Available to Purchase

Jiaxuan Li, Hongwei Zhu, Taowei Wang, Zelin Gao, Xiaotong Chen, Gang Xu, Bing Liu, Yaping Tang
Proc. ASME. ICONE31, Volume 2: Nuclear Fuel and Material, Reactor Physics and Transport Theory, and Fuel Cycle Technology, V002T02A066, August 4–8, 2024
Publisher: American Society of Mechanical Engineers
Paper No: ICONE31-137055
https://doi.org/10.1115/ICONE31-137055
View Paper titled, Adsorption and Diffusion of Silver on SiC(111) and ZrC(111) Surfaces: A First Principles Study
Open the PDF for Adsorption and Diffusion of Silver on SiC(111) and ZrC(111) Surfaces: A First Principles Study in another window
Topics: Diffusion (Physics), Silicon carbide, Silver
Proceedings Papers

Irradiation-Thermal-Mechanical Coupling Behaviors of a Typical TRISO/SiC Fuel Element Based on Actual Distribution

Available to Purchase

Zhang Liangjie, Chen Ping, Liu Shichao, Wang Haoyu, Wei Chong, Pan Xiaoqiang
Proc. ASME. ICONE31, Volume 2: Nuclear Fuel and Material, Reactor Physics and Transport Theory, and Fuel Cycle Technology, V002T02A045, August 4–8, 2024
Publisher: American Society of Mechanical Engineers
Paper No: ICONE31-135863
https://doi.org/10.1115/ICONE31-135863
View Paper titled, Irradiation-Thermal-Mechanical Coupling Behaviors of a Typical TRISO/SiC Fuel Element Based on Actual Distribution
Open the PDF for Irradiation-Thermal-Mechanical Coupling Behaviors of a Typical TRISO/SiC Fuel Element Based on Actual Distribution in another window
Topics: Finite element model, Fuels, Irradiation (Radiation exposure), Silicon carbide
Proceedings Papers

Numerical Simulation Research on Irradiation-Thermal-Mechanical Behavior of CDM Fuel in Different Types of Reactors

Available to Purchase

Changbing Tang, Yuanming Li, Haoyu Liao
Proc. ASME. ICONE31, Volume 2: Nuclear Fuel and Material, Reactor Physics and Transport Theory, and Fuel Cycle Technology, V002T02A044, August 4–8, 2024
Publisher: American Society of Mechanical Engineers
Paper No: ICONE31-135696
https://doi.org/10.1115/ICONE31-135696
View Paper titled, Numerical Simulation Research on Irradiation-Thermal-Mechanical Behavior of CDM Fuel in Different Types of Reactors
Open the PDF for Numerical Simulation Research on Irradiation-Thermal-Mechanical Behavior of CDM Fuel in Different Types of Reactors in another window
Topics: Computer simulation, Failure, Fuels, Irradiation (Radiation exposure)
Proceedings Papers

Calculation of Radiation Field and Shutdown Dose Rate for Fusion Reactor Based on cosRMC

Available to Purchase

Shichang Liu, Zhenyu Wang, Rui Che
Proc. ASME. ICONE31, Volume 2: Nuclear Fuel and Material, Reactor Physics and Transport Theory, and Fuel Cycle Technology, V002T02A027, August 4–8, 2024
Publisher: American Society of Mechanical Engineers
Paper No: ICONE31-134661
https://doi.org/10.1115/ICONE31-134661
View Paper titled, Calculation of Radiation Field and Shutdown Dose Rate for Fusion Reactor Based on cosRMC
Open the PDF for Calculation of Radiation Field and Shutdown Dose Rate for Fusion Reactor Based on cosRMC in another window
Topics: Fusion reactors, Radiation (Physics), Algorithms, Resolution (Optics), Accuracy and precision, Computational methods, Geometry, Nuclear design, Particulate matter, Safety