1-20 of 555
Neutrons
Close
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 Dynamic Rod Measurement Method Based on Torch Software Package for PWR

Available to Purchase

Yun Cai, TianYa Li, Rui Guo, Tongxian Liu, Qing Li, LingFang Yang, Wenbo Zhao
Proc. ASME. ICONE31, Volume 1: Nuclear Plant Operation and Maintenance, Engineering and Modification, Operation Life Extension (OLE), and Life Cycle, V001T01A026, August 4–8, 2024
Publisher: American Society of Mechanical Engineers
Paper No: ICONE31-135284
https://doi.org/10.1115/ICONE31-135284
View Paper titled, Research on Dynamic Rod Measurement Method Based on Torch Software Package for PWR
Open the PDF for Research on Dynamic Rod Measurement Method Based on Torch Software Package for PWR in another window
Topics: Computer software, Pressurized water reactors, Spacetime, Neutrons, China, Electricity (Physics), Errors, Nuclear power, Physics, Power stations
Proceedings Papers

Evaluating the Impact of Neutron Absorber Materials on Spent Fuel Pool Rack Criticality Using OpenMC Monte Carlo Code

Available to Purchase

Busra Buyrukcu, Eray Buyrukcu, Dzianis Litskevich, Karl Whittle
Proc. ASME. ICONE31, Volume 1: Nuclear Plant Operation and Maintenance, Engineering and Modification, Operation Life Extension (OLE), and Life Cycle, V001T01A046, August 4–8, 2024
Publisher: American Society of Mechanical Engineers
Paper No: ICONE31-137004
https://doi.org/10.1115/ICONE31-137004
View Paper titled, Evaluating the Impact of Neutron Absorber Materials on Spent Fuel Pool Rack Criticality Using OpenMC Monte Carlo Code
Open the PDF for Evaluating the Impact of Neutron Absorber Materials on Spent Fuel Pool Rack Criticality Using OpenMC Monte Carlo Code in another window
Topics: Neutrons, Spent nuclear fuels
Proceedings Papers

Load-Following Control of Nuclear Reactor Using Variable-Order Fuzzy Fractional PID Controller Based on the Fractional-Space Neutron Point Kinetics Model

Available to Purchase

Hetao Sun, Hailemichael Guadie Mengsitu, Xiuchun Luan, Jie Zhou, Junling Wang, Zhida Yang
Proc. ASME. ICONE31, Volume 1: Nuclear Plant Operation and Maintenance, Engineering and Modification, Operation Life Extension (OLE), and Life Cycle, V001T01A027, August 4–8, 2024
Publisher: American Society of Mechanical Engineers
Paper No: ICONE31-135371
https://doi.org/10.1115/ICONE31-135371
View Paper titled, Load-Following Control of Nuclear Reactor Using Variable-Order Fuzzy Fractional PID Controller Based on the Fractional-Space Neutron Point Kinetics Model
Open the PDF for Load-Following Control of Nuclear Reactor Using Variable-Order Fuzzy Fractional PID Controller Based on the Fractional-Space Neutron Point Kinetics Model in another window
Topics: Control equipment, Neutrons, Nuclear reactors, Stress
Proceedings Papers

Ways to Solve the Safe Operation of VVER-1000 Reactors in Case of Loss of Original Rod Cluster Control Assemblies Supply

Available to Purchase

Oleksandr Mazurok, Valeriy Zuyok, Vadym Ivanov, Mykhaylo Tretyakov
Proc. ASME. ICONE31, Volume 1: Nuclear Plant Operation and Maintenance, Engineering and Modification, Operation Life Extension (OLE), and Life Cycle, V001T01A018, August 4–8, 2024
Publisher: American Society of Mechanical Engineers
Paper No: ICONE31-134916
https://doi.org/10.1115/ICONE31-134916
View Paper titled, Ways to Solve the Safe Operation of VVER-1000 Reactors in Case of Loss of Original Rod Cluster Control Assemblies Supply
Open the PDF for Ways to Solve the Safe Operation of VVER-1000 Reactors in Case of Loss of Original Rod Cluster Control Assemblies Supply in another window
Topics: Absorption, Boron, Cladding systems (Building), Density, Dysprosium, Europium, Fuels, Hafnium, Neutrons, Nuclear power stations
Proceedings Papers

Implementation of Domain Decomposition Parallel and gCMFD in MOCP: Method of Characteristics for Pebble-Bed

Available to Purchase

Chen Hao, Yu Chen Wen, Yi Zhen Wang
Proc. ASME. ICONE31, Volume 2: Nuclear Fuel and Material, Reactor Physics and Transport Theory, and Fuel Cycle Technology, V002T02A033, August 4–8, 2024
Publisher: American Society of Mechanical Engineers
Paper No: ICONE31-134979
https://doi.org/10.1115/ICONE31-134979
View Paper titled, Implementation of Domain Decomposition Parallel and gCMFD in MOCP: Method of Characteristics for Pebble-Bed
Open the PDF for Implementation of Domain Decomposition Parallel and gCMFD in MOCP: Method of Characteristics for Pebble-Bed in another window
Topics: Geometry, Neutrons, Simulation, Stress, Very high temperature reactors
Proceedings Papers

Research on the ODR-VS Method Applicable to Various Geometric Models

Available to Purchase

Zhiyuan Feng, Jingang Liang, Wenli Guo, Kan Wang
Proc. ASME. ICONE31, Volume 2: Nuclear Fuel and Material, Reactor Physics and Transport Theory, and Fuel Cycle Technology, V002T02A032, August 4–8, 2024
Publisher: American Society of Mechanical Engineers
Paper No: ICONE31-134943
https://doi.org/10.1115/ICONE31-134943
View Paper titled, Research on the ODR-VS Method Applicable to Various Geometric Models
Open the PDF for Research on the ODR-VS Method Applicable to Various Geometric Models in another window
Topics: Ceramics, Cylinders, Discrete element methods, Ductility, Fuels, Geometric modeling, Metals, Modeling, Neutrons, Nuclear fuels
Proceedings Papers

Improved Athermal Recombination Corrected DPA Model for Displacement Damage Cross Section Calculation

Available to Purchase

Wen Yin, Tiejun Zu, Liangzhi Cao
Proc. ASME. ICONE31, Volume 2: Nuclear Fuel and Material, Reactor Physics and Transport Theory, and Fuel Cycle Technology, V002T02A037, August 4–8, 2024
Publisher: American Society of Mechanical Engineers
Paper No: ICONE31-135163
https://doi.org/10.1115/ICONE31-135163
View Paper titled, Improved Athermal Recombination Corrected DPA Model for Displacement Damage Cross Section Calculation
Open the PDF for Improved Athermal Recombination Corrected DPA Model for Displacement Damage Cross Section Calculation in another window
Topics: Damage, Displacement, Electrons, Neutrons, Particulate matter
Proceedings Papers

High-Order Harmonics Calculation for the Power Reconstruction of 3D Pin-Scale Whole-Core

Available to Purchase

Zhinan Xie, Chen Hao, Wen Yin
Proc. ASME. ICONE31, Volume 2: Nuclear Fuel and Material, Reactor Physics and Transport Theory, and Fuel Cycle Technology, V002T02A061, August 4–8, 2024
Publisher: American Society of Mechanical Engineers
Paper No: ICONE31-136320
https://doi.org/10.1115/ICONE31-136320
View Paper titled, High-Order Harmonics Calculation for the Power Reconstruction of 3D Pin-Scale Whole-Core
Open the PDF for High-Order Harmonics Calculation for the Power Reconstruction of 3D Pin-Scale Whole-Core in another window
Topics: Diffusion (Physics), Heating, Low temperature, Manufacturing, Neutrons
Proceedings Papers

Development and Initial Analysis of a Neutron Diffusion Model for TEPLATOR Using COMSOL Multiphysics Software

Available to Purchase

Dipanjan Ray, Martin Lovecký, Jiří Závorka, Radek Škoda
Proc. ASME. ICONE31, Volume 2: Nuclear Fuel and Material, Reactor Physics and Transport Theory, and Fuel Cycle Technology, V002T02A013, August 4–8, 2024
Publisher: American Society of Mechanical Engineers
Paper No: ICONE31-133182
https://doi.org/10.1115/ICONE31-133182
View Paper titled, Development and Initial Analysis of a Neutron Diffusion Model for TEPLATOR Using COMSOL Multiphysics Software
Open the PDF for Development and Initial Analysis of a Neutron Diffusion Model for TEPLATOR Using COMSOL Multiphysics Software in another window
Topics: Computer software, Diffusion (Physics), Neutrons
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

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

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 Preconditioning Method Based on Strongly Implicit Procedure for the Multi- Diagonal Equation

Available to Purchase

Bo Tan, Haojie Zhang, Yutong Wen, Ding She
Proc. ASME. ICONE31, Volume 2: Nuclear Fuel and Material, Reactor Physics and Transport Theory, and Fuel Cycle Technology, V002T02A016, August 4–8, 2024
Publisher: American Society of Mechanical Engineers
Paper No: ICONE31-133656
https://doi.org/10.1115/ICONE31-133656
View Paper titled, A Preconditioning Method Based on Strongly Implicit Procedure for the Multi- Diagonal Equation
Open the PDF for A Preconditioning Method Based on Strongly Implicit Procedure for the Multi- Diagonal Equation in another window
Topics: Algorithms, Convection, Cylinders, Diffusion (Physics), Heat conduction, Neutrons, Nuclear engineering, Numerical analysis, Partial differential equations, Physics
Proceedings Papers

A Method Using Strong Tracking Filter for Compensating the Response Delay of Self-Powered Neutron Detectors

Available to Purchase

Shiyu Liu, Qingmin Zhang, Jinliang Liu, Yaodong Sang, Zhuang Shao, Kangfu Zhu
Proc. ASME. ICONE31, Volume 3: I&C, Digital Control, and Influence of Human Factors, V003T03A003, August 4–8, 2024
Publisher: American Society of Mechanical Engineers
Paper No: ICONE31-130885
https://doi.org/10.1115/ICONE31-130885
View Paper titled, A Method Using Strong Tracking Filter for Compensating the Response Delay of Self-Powered Neutron Detectors
Open the PDF for A Method Using Strong Tracking Filter for Compensating the Response Delay of Self-Powered Neutron Detectors in another window
Topics: Delays, Filters, Neutrons, Noise (Sound), Sensors
Proceedings Papers

A Fuzzy Control Method for Adjusting the Peak Value of Power Axial Distribution Based on Distributed Parameter Model

Available to Purchase

Airan Dang, Bowen Tu, Xiuchun Luan
Proc. ASME. ICONE31, Volume 3: I&C, Digital Control, and Influence of Human Factors, V003T03A013, August 4–8, 2024
Publisher: American Society of Mechanical Engineers
Paper No: ICONE31-135044
https://doi.org/10.1115/ICONE31-135044
View Paper titled, A Fuzzy Control Method for Adjusting the Peak Value of Power Axial Distribution Based on Distributed Parameter Model
Open the PDF for A Fuzzy Control Method for Adjusting the Peak Value of Power Axial Distribution Based on Distributed Parameter Model in another window
Topics: Distributed parameter models, Fuzzy control, Steady state, Control equipment, Diffusion (Physics), Neutrons, Stress, Distributed parameter systems, Simulation results, Spacetime
Proceedings Papers

A Study on the Burnup Effect of Silver Self-Powered Neutron Detector

Available to Purchase

Yaodong Sang, Bangjie Deng, Shiyu Liu, Qingmin Zhang
Proc. ASME. ICONE31, Volume 3: I&C, Digital Control, and Influence of Human Factors, V003T03A005, August 4–8, 2024
Publisher: American Society of Mechanical Engineers
Paper No: ICONE31-134377
https://doi.org/10.1115/ICONE31-134377
View Paper titled, A Study on the Burnup Effect of Silver Self-Powered Neutron Detector
Open the PDF for A Study on the Burnup Effect of Silver Self-Powered Neutron Detector in another window
Topics: Neutrons, Sensors, Silver
Proceedings Papers

Feasibility Study of Variable Spectrum Molten Salt Reactor by Adjusting Fuel Salt Compositions for the LiF-BeF 2 -ZrF 4 -UF 4 System

Available to Purchase

Naoto Aizawa, Hiroki Shishido, Koji Fujikura
Proc. ASME. ICONE31, Volume 4: SMRs, Advanced Reactors, and Fusion, V004T04A034, August 4–8, 2024
Publisher: American Society of Mechanical Engineers
Paper No: ICONE31-134672
https://doi.org/10.1115/ICONE31-134672
View Paper titled, Feasibility Study of Variable Spectrum Molten Salt Reactor by Adjusting Fuel Salt Compositions for the LiF-BeF 2 -ZrF 4 -UF 4 System
Open the PDF for Feasibility Study of Variable Spectrum Molten Salt Reactor by Adjusting Fuel Salt Compositions for the LiF-BeF 2 -ZrF 4 -UF 4 System in another window
Topics: Fuels, Molten salt reactors, Neutrons
Proceedings Papers

Conceptual Design and Feasibility Analysis of a Modular Supercritical CO 2 Fast Reactor Core

Available to Purchase

Guihua Lai, Tian Wang, Ding She, Hong Wang
Proc. ASME. ICONE31, Volume 4: SMRs, Advanced Reactors, and Fusion, V004T04A045, August 4–8, 2024
Publisher: American Society of Mechanical Engineers
Paper No: ICONE31-135206
https://doi.org/10.1115/ICONE31-135206
View Paper titled, Conceptual Design and Feasibility Analysis of a Modular Supercritical CO 2 Fast Reactor Core
Open the PDF for Conceptual Design and Feasibility Analysis of a Modular Supercritical CO 2 Fast Reactor Core in another window
Topics: Conceptual design, Fast neutron reactors, Small modular reactors, Supercritical carbon dioxide, Safety, Temperature, Design, Fuel rods, Heat, Particulate matter
Proceedings Papers

Thermo-Neutronics Coupled Simulation of a Heat Pipe Reactor Based on OpenMC/COMSOL

Available to Purchase

Jingyu Nie, Binqian Li, Yingwei Wu, Jing Zhang, Guoliang Zhang, Qisen Ren, Yanan He, Guanghui Su
Proc. ASME. ICONE31, Volume 4: SMRs, Advanced Reactors, and Fusion, V004T04A047, August 4–8, 2024
Publisher: American Society of Mechanical Engineers
Paper No: ICONE31-135246
https://doi.org/10.1115/ICONE31-135246
View Paper titled, Thermo-Neutronics Coupled Simulation of a Heat Pipe Reactor Based on OpenMC/COMSOL
Open the PDF for Thermo-Neutronics Coupled Simulation of a Heat Pipe Reactor Based on OpenMC/COMSOL in another window
Topics: Heat pipes, Simulation, Neutrons, Physics, Cross section (Physics), Databases, Density, Design, Modeling, Nuclear reactors
Proceedings Papers

Preliminary Core Design Analysis of Core Criticality and Heat Transfer of the All-Solid State Micro-Reactor

Available to Purchase

Takeshi Koike, Koji Asano, Mizuki Yamada, Satoru Kamohara, Tadakatsu Yodo, Nozomu Murakami
Proc. ASME. ICONE31, Volume 4: SMRs, Advanced Reactors, and Fusion, V004T04A037, August 4–8, 2024
Publisher: American Society of Mechanical Engineers
Paper No: ICONE31-135017
https://doi.org/10.1115/ICONE31-135017
View Paper titled, Preliminary Core Design Analysis of Core Criticality and Heat Transfer of the All-Solid State Micro-Reactor
Open the PDF for Preliminary Core Design Analysis of Core Criticality and Heat Transfer of the All-Solid State Micro-Reactor in another window
Topics: Design, Heat transfer, Neutrons, Safety, Reliability, Carbon, Fuels, Graphite, Heat, Light water reactors