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Proceedings Papers

Development of an MPS Code for Corium Behavior Analysis

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Lijun Jian, Hongfan Lu, Peng Yu, Yidan Yuan
Proc. ASME. ICONE29, Volume 8: Computational Fluid Dynamics (CFD) and Applications, V008T08A013, August 8–12, 2022
Publisher: American Society of Mechanical Engineers
Paper No: ICONE29-91422
https://doi.org/10.1115/ICONE29-91422
View Paper titled, Development of an MPS Code for Corium Behavior Analysis
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Topics: Accidents, Alloys, Collapse, Deformation, Drops, Enthalpy, Fukushima nuclear disaster, Japan, 2011, Heat transfer, Melting, Oscillations
Proceedings Papers

Analysis of UO 2 -BeO Fuel Performance During Normal Conditions and RIA

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Yanan He, Yingwei Wu, Shihuai Wang, Bowen Qiu, G. H. Su
Proc. ASME. ICONE26, Volume 9: Student Paper Competition, V009T16A070, July 22–26, 2018
Publisher: American Society of Mechanical Engineers
Paper No: ICONE26-82076
https://doi.org/10.1115/ICONE26-82076
View Paper titled, Analysis of UO 2 -BeO Fuel Performance During Normal Conditions and RIA
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Topics: Fuels, Composite materials, Light water reactors, Accidents, Nuclear fission, Thermal conductivity, Thermal properties, Cladding systems (Building), Coolants, Enthalpy
Proceedings Papers

Penetration Jet Impingement Calculation in Engineering Application

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Tong Wu, Ying Zhou, Tao Qi
Proc. ASME. ICONE25, Volume 4: Nuclear Safety, Security, Non-Proliferation and Cyber Security; Risk Management, V004T06A022, July 2–6, 2017
Publisher: American Society of Mechanical Engineers
Paper No: ICONE25-67096
https://doi.org/10.1115/ICONE25-67096
View Paper titled, Penetration Jet Impingement Calculation in Engineering Application
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Topics: Drops, Engineering systems and industry applications, Enthalpy, Flashing, Floods, Flow (Dynamics), Fluids, Hazard analysis, Hot water, Jets
Proceedings Papers

The Impacts of Scale Effect on Flow Patterns in a Supersonic Steam Injector

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Masaya Fujishiro, Yutaka Abe, Akiko Kaneko
Proc. ASME. ICONE25, Volume 9: Student Paper Competition, V009T15A031, July 2–6, 2017
Publisher: American Society of Mechanical Engineers
Paper No: ICONE25-67009
https://doi.org/10.1115/ICONE25-67009
View Paper titled, The Impacts of Scale Effect on Flow Patterns in a Supersonic Steam Injector
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Topics: Ejectors, Flow (Dynamics), Water, Steam, Accidents, Nuclear power stations, Pressure, Safety, Condensation, Condensers (steam plant)
Proceedings Papers

Numerical Investigation of Spacer Effects on Heat Transfer Enhancement in a Vertical Annular Channel at Supercritical Pressure

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Jinsong Pan, Yao Xiao, Hanyang Gu
Proc. ASME. ICONE25, Volume 8: Computational Fluid Dynamics (CFD) and Coupled Codes; Nuclear Education, Public Acceptance and Related Issues, V008T09A030, July 2–6, 2017
Publisher: American Society of Mechanical Engineers
Paper No: ICONE25-66911
https://doi.org/10.1115/ICONE25-66911
View Paper titled, Numerical Investigation of Spacer Effects on Heat Transfer Enhancement in a Vertical Annular Channel at Supercritical Pressure
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Topics: Heat transfer, Pressure, Computational fluid dynamics, Fuel rods, Supercritical fluids, Supercritical water reactors, Computer simulation, Economics , Enthalpy, Fluids
Proceedings Papers

Application of Fuzzy Weighted Support Vector Regression to Accidents Condition Monitoring of Nuclear Power Plant

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B. T. Jiang, J. W. Hines, F. Y. Zhao
Proc. ASME. ICONE24, Volume 2: Smart Grids, Grid Stability, and Offsite and Emergency Power; Advanced and Next Generation Reactors, Fusion Technology; Safety, Security, and Cyber Security; Codes, Standards, Conformity Assessment, Licensing, and Regulatory Issues, V002T07A014, June 26–30, 2016
Publisher: American Society of Mechanical Engineers
Paper No: ICONE24-60983
https://doi.org/10.1115/ICONE24-60983
View Paper titled, Application of Fuzzy Weighted Support Vector Regression to Accidents Condition Monitoring of Nuclear Power Plant
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Topics: Accidents, Condition monitoring, Nuclear power stations, Support vector machines, Artificial neural networks, Fuels, Temperature, Transients (Dynamics), Boron, Computers
Proceedings Papers

Evaluation of Thermodynamic Properties of Cerium in Liquid Cadmium Cathode Within LiCl-KCl Salt System

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Dalsung Yoon, Supathorn Phongikaroon
Proc. ASME. ICONE24, Volume 5: Student Paper Competition, V005T15A054, June 26–30, 2016
Publisher: American Society of Mechanical Engineers
Paper No: ICONE24-60725
https://doi.org/10.1115/ICONE24-60725
View Paper titled, Evaluation of Thermodynamic Properties of Cerium in Liquid Cadmium Cathode Within LiCl-KCl Salt System
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Topics: Circuits, Enthalpy, Entropy, Gibbs' free energy, Intermetallic compounds, Metals, Temperature
Proceedings Papers

Research on Modular Modeling Method of Reactor Coolant System Based on THEATRe

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Bo Shi, Zhao-Fei Tian
Proc. ASME. ICONE22, Volume 2A: Thermal Hydraulics, V02AT09A057, July 7–11, 2014
Publisher: American Society of Mechanical Engineers
Paper No: ICONE22-30450
https://doi.org/10.1115/ICONE22-30450
View Paper titled, Research on Modular Modeling Method of Reactor Coolant System Based on THEATRe
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Topics: Modeling, Nuclear reactor coolants, Pressure, Boilers, Computer software, Coolants, Enthalpy, Momentum, Nuclear power stations, Pumps
Proceedings Papers

Experimental Study of Heat Transfer to Supercritical Pressure Water Flowing in a 2×2 Rod Bundle

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Han Wang, Qincheng Bi, Linchuan Wang, Haicai Lv, Laurence K. H. Leung
Proc. ASME. ICONE22, Volume 2A: Thermal Hydraulics, V02AT09A040, July 7–11, 2014
Publisher: American Society of Mechanical Engineers
Paper No: ICONE22-30313
https://doi.org/10.1115/ICONE22-30313
View Paper titled, Experimental Study of Heat Transfer to Supercritical Pressure Water Flowing in a 2×2 Rod Bundle
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Topics: Fuel rods, Heat transfer, Pressure, Water, Heat flux, Flow (Dynamics), Pressure drop, Wall temperature, Annulus, Corners (Structural elements)
Proceedings Papers

Subchannel Analysis of Large Power PWR

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Fei Xie
Proc. ASME. ICONE22, Volume 2A: Thermal Hydraulics, V02AT09A054, July 7–11, 2014
Publisher: American Society of Mechanical Engineers
Paper No: ICONE22-30428
https://doi.org/10.1115/ICONE22-30428
View Paper titled, Subchannel Analysis of Large Power PWR
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Topics: Pressurized water reactors, Boiling, Design, Enthalpy, Steady state
Proceedings Papers

Two-Way Coupling Between the Reactor Dynamics Code DYN3D and the Fuel Performance Code TRANSURANUS at Assembly Level

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L. Holt, U. Rohde, M. Seidl, A. Schubert, P. Van Uffelen, R. Macián-Juan
Proc. ASME. ICONE22, Volume 5: Innovative Nuclear Power Plant Design and New Technology Application; Student Paper Competition, V005T17A052, July 7–11, 2014
Publisher: American Society of Mechanical Engineers
Paper No: ICONE22-30812
https://doi.org/10.1115/ICONE22-30812
View Paper titled, Two-Way Coupling Between the Reactor Dynamics Code DYN3D and the Fuel Performance Code TRANSURANUS at Assembly Level
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Topics: Dynamics (Mechanics), Fuels, Manufacturing, Thermal hydraulics, Transients (Dynamics), Modeling, Temperature, Heat transfer, Pressurized water reactors, Accidents
Proceedings Papers

A Prediction of the Leakage Through Cracks for Leak Before Break

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Jing Zhang, Yingwei Wu, Lei Ding, Hongwei Qiao, Pengzhou Li, Guanghui Su, Suizheng Qiu, Wenxi Tian
Proc. ASME. ICONE22, Volume 2B: Thermal Hydraulics, V02BT09A018, July 7–11, 2014
Publisher: American Society of Mechanical Engineers
Paper No: ICONE22-30708
https://doi.org/10.1115/ICONE22-30708
View Paper titled, A Prediction of the Leakage Through Cracks for Leak Before Break
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Topics: Fracture (Materials), Leakage, Leak-before-break, Flow (Dynamics), Surface roughness, Corners (Structural elements), Displacement, Enthalpy, Fluids, Friction
Proceedings Papers

Analysis of the Control Rod Drop Accident (CRDA) for Lungmen ABWR

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Ai-Ling Ho, Jong-Rong Wang, Hao-Tzu Lin, Chunkuan Shih
Proc. ASME. ICONE22, Volume 3: Next Generation Reactors and Advanced Reactors; Nuclear Safety and Security, V003T06A035, July 7–11, 2014
Publisher: American Society of Mechanical Engineers
Paper No: ICONE22-30838
https://doi.org/10.1115/ICONE22-30838
View Paper titled, Analysis of the Control Rod Drop Accident (CRDA) for Lungmen ABWR
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Topics: Accidents, Fuels, Cladding systems (Building), Failure, Fuel rods, Damage, High temperature, Melting, Transients (Dynamics), Boiling water reactors
Proceedings Papers

Numerical Analysis of Crust Behavior of Molten Core and Concrete Interaction by Using MPS Method

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Takeo Watanabe, Yoshiaki Oka
Proc. ASME. ICONE22, Volume 6: Nuclear Education, Public Acceptance and Related Issues; Instrumentation and Controls (I&C); Fusion Engineering; Beyond Design Basis Events, V006T15A013, July 7–11, 2014
Publisher: American Society of Mechanical Engineers
Paper No: ICONE22-30384
https://doi.org/10.1115/ICONE22-30384
View Paper titled, Numerical Analysis of Crust Behavior of Molten Core and Concrete Interaction by Using MPS Method
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Topics: Concretes, Numerical analysis, Particulate matter, Heat transfer, Bridges (Structures), Enthalpy, Water, Radiation (Physics), Ablation (Vaporization technology), Fluids
Proceedings Papers

Safety Analysis of a High Breeding Fast Reactor Cooled by Supercritical-Pressure Light Water: Accidents and Abnormal Transients at Supercritical Pressure

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Rui Guo, Yoshiaki Oka
Proc. ASME. ICONE22, Volume 3: Next Generation Reactors and Advanced Reactors; Nuclear Safety and Security, V003T06A007, July 7–11, 2014
Publisher: American Society of Mechanical Engineers
Paper No: ICONE22-30185
https://doi.org/10.1115/ICONE22-30185
View Paper titled, Safety Analysis of a High Breeding Fast Reactor Cooled by Supercritical-Pressure Light Water: Accidents and Abnormal Transients at Supercritical Pressure
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Topics: Accidents, Fast neutron reactors, Pressure, Safety, Transients (Dynamics), Water, Cladding systems (Building), Conceptual design, Enthalpy, Fuel rods
Proceedings Papers

AP1000 3D Rod Ejection Reactor Core Thermal Analyses

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Huimin Qin
Proc. ASME. ICONE21, Volume 4: Thermal Hydraulics, V004T09A087, July 29–August 2, 2013
Publisher: American Society of Mechanical Engineers
Paper No: ICONE21-16354
https://doi.org/10.1115/ICONE21-16354
View Paper titled, AP1000 3D Rod Ejection Reactor Core Thermal Analyses
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Topics: Acceptance criteria, Accidents, Cladding systems (Building), Computers, Enthalpy, Equilibrium (Physics), Failure mechanisms, Fuels, Nuclear industry, Physics
Proceedings Papers

High Breeding Core of a Supercritical-Pressure Light Water Cooled Fast Reactor

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Taishi Yoshida, Yoshiaki Oka
Proc. ASME. ICONE21, Volume 2: Plant Systems, Construction, Structures and Components; Next Generation Reactors and Advanced Reactors, V002T05A019, July 29–August 2, 2013
Publisher: American Society of Mechanical Engineers
Paper No: ICONE21-15753
https://doi.org/10.1115/ICONE21-15753
View Paper titled, High Breeding Core of a Supercritical-Pressure Light Water Cooled Fast Reactor
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Topics: Fast neutron reactors, Pressure, Water, Fuels, Coolants, Rods, Cooling, Breeder reactors, Collisions (Physics), Cross section (Physics)
Proceedings Papers

Sensitivity Studies on the Influence of Shutdown Control Assembly Banks Arrangement in Rod Control Assembly Banks Withdrawal From a Subcritical Condition

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Dawei Cui, Yanhua Cheng, Yulong Mao, Jun Chen
Proc. ASME. ICONE21, Volume 3: Nuclear Safety and Security; Codes, Standards, Licensing and Regulatory Issues; Computational Fluid Dynamics and Coupled Codes, V003T06A014, July 29–August 2, 2013
Publisher: American Society of Mechanical Engineers
Paper No: ICONE21-15361
https://doi.org/10.1115/ICONE21-15361
View Paper titled, Sensitivity Studies on the Influence of Shutdown Control Assembly Banks Arrangement in Rod Control Assembly Banks Withdrawal From a Subcritical Condition
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Topics: Manufacturing, Power stations, Accidents, Computational methods, Enthalpy, Thermal energy, Transients (Dynamics)
Proceedings Papers

Experimental Study on Adsorption of Carbon Dioxide on 13X Molecular Sieve for Coolant Helium Purification

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Hua Chang, Tao Ma, Ling Liu, Hua-Qiang Yin, Xue-Dong He
Proc. ASME. ICONE21, Volume 2: Plant Systems, Construction, Structures and Components; Next Generation Reactors and Advanced Reactors, V002T03A009, July 29–August 2, 2013
Publisher: American Society of Mechanical Engineers
Paper No: ICONE21-15362
https://doi.org/10.1115/ICONE21-15362
View Paper titled, Experimental Study on Adsorption of Carbon Dioxide on 13X Molecular Sieve for Coolant Helium Purification
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Topics: Carbon dioxide, Coolants, Helium, Very high temperature reactors, Enthalpy, Equilibrium (Physics), Mass transfer, Pressure, Roads, Temperature
Proceedings Papers

Stability Analysis of a Supercritical Water Natural Circulation Loop

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ZhongChun Li, JiYang Yu, XiaoMing Song
Proc. ASME. ICONE20-POWER2012, Volume 3: Thermal-Hydraulics; Turbines, Generators, and Auxiliaries, 687-696, July 30–August 3, 2012
Publisher: American Society of Mechanical Engineers
Paper No: ICONE20-POWER2012-55081
https://doi.org/10.1115/ICONE20-POWER2012-55081
View Paper titled, Stability Analysis of a Supercritical Water Natural Circulation Loop
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Topics: Stability, Water, Enthalpy, Supercritical water reactors, Numerical analysis, Physics