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Proceedings Papers

Analysis of Transient Corium Pool Structure in the Lower Plenum of Reactor Vessel

Liang Chen, Hua Pang, Ximing Xie, Lei Zhong, Rong Cai
Proc. ASME. ICONE2020, Volume 2: Nuclear Policy; Nuclear Safety, Security, and Cyber Security; Operating Plant Experience; Probabilistic Risk Assessments; SMR and Advanced Reactors, V002T08A041, August 4–5, 2020
Publisher: American Society of Mechanical Engineers
Paper No: ICONE2020-16470
https://doi.org/10.1115/ICONE2020-16470
View Paper titled, Analysis of Transient Corium Pool Structure in the Lower Plenum of Reactor Vessel
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Topics: Accidents, Reactor vessels, Transients (Dynamics), Vessels, Density, Heat flux, Heavy metals, China, Coolants, Critical heat flux
Proceedings Papers

Stratification and Heat Transfer of Molten Corium Pool for In-Vessel Retention

Qingan Xiang, Jian Deng, Dahuan Zhu, Xiaoli Wu, Jinsheng Bi, Baowen Chen, Rong Cai, Libo Qian, Yugao Ma
Proc. ASME. ICONE2020, Volume 2: Nuclear Policy; Nuclear Safety, Security, and Cyber Security; Operating Plant Experience; Probabilistic Risk Assessments; SMR and Advanced Reactors, V002T08A053, August 4–5, 2020
Publisher: American Society of Mechanical Engineers
Paper No: ICONE2020-16742
https://doi.org/10.1115/ICONE2020-16742
View Paper titled, Stratification and Heat Transfer of Molten Corium Pool for In-Vessel Retention
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Topics: Heat transfer, Heavy metals, Vessels
Proceedings Papers

A Core Design of Innovative Breeder BWR

Guo Rui, Akifumi Yamaji, Yun Cai, Xingjie Peng
Proc. ASME. ICONE26, Volume 1: Operations and Maintenance, Engineering, Modifications, Life Extension, Life Cycle, and Balance of Plant; Instrumentation and Control (I&C) and Influence of Human Factors; Innovative Nuclear Power Plant Design and SMRs, V001T13A017, July 22–26, 2018
Publisher: American Society of Mechanical Engineers
Paper No: ICONE26-82079
https://doi.org/10.1115/ICONE26-82079
View Paper titled, A Core Design of Innovative Breeder BWR
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Topics: Boiling water reactors, Design, Manufacturing, Water, Atoms, Cooling, Fuels, Neutrons, Economics , Heavy metals
Proceedings Papers

Preliminary Neutronics and Thermal-Hydraulics Study on Thorium-Based HTR-PM With Outer Breeding Zone

Qiudong Wang, Bing Xia, Jiong Guo, Ding She, Lei Shi, Zuoyi Zhang
Proc. ASME. ICONE26, Volume 5: Advanced Reactors and Fusion Technologies; Codes, Standards, Licensing, and Regulatory Issues, V005T05A019, July 22–26, 2018
Publisher: American Society of Mechanical Engineers
Paper No: ICONE26-81975
https://doi.org/10.1115/ICONE26-81975
View Paper titled, Preliminary Neutronics and Thermal-Hydraulics Study on Thorium-Based HTR-PM With Outer Breeding Zone
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Topics: Thermal hydraulics, Fuels, Design, Heavy metals, Temperature, Accidents, Optimization, Particulate matter, Safety
Proceedings Papers

Neutronic Study on a New Concept of Accelerator Driven Subcritical System in China

Jinyang Li, Long Gu, Cunfeng Yao, Dawei Wang, Tianji Peng, Yanlei Zhu
Proc. ASME. ICONE26, Volume 5: Advanced Reactors and Fusion Technologies; Codes, Standards, Licensing, and Regulatory Issues, V005T05A007, July 22–26, 2018
Publisher: American Society of Mechanical Engineers
Paper No: ICONE26-81329
https://doi.org/10.1115/ICONE26-81329
View Paper titled, Neutronic Study on a New Concept of Accelerator Driven Subcritical System in China
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Topics: China, Cycles, Design, Doppler effect, Flow (Dynamics), Gravity (Force), Heavy metals, Neutron sources, Neutrons, Physics
Proceedings Papers

Evaluation of the Kinetics of Molten Pool Stratification in Case of In-Vessel Melt Retention Strategy

L. Carénini, F. Fichot
Proc. ASME. ICONE26, Volume 7: Decontamination and Decommissioning, Radiation Protection, and Waste Management; Mitigation Strategies for Beyond Design Basis Events, V007T11A013, July 22–26, 2018
Publisher: American Society of Mechanical Engineers
Paper No: ICONE26-82243
https://doi.org/10.1115/ICONE26-82243
View Paper titled, Evaluation of the Kinetics of Molten Pool Stratification in Case of In-Vessel Melt Retention Strategy
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Topics: Vessels, Transients (Dynamics), Light water reactors, Chemistry, Pressurized water reactors, Accidents, Flux (Metallurgy), Heat, Heat flux, Metals
Proceedings Papers

Hydraulic Investigations on Free Surface Flow of ADS Windowless Target

Chen Hu
Proc. ASME. ICONE25, Volume 6: Thermal-Hydraulics, V006T08A086, July 2–6, 2017
Publisher: American Society of Mechanical Engineers
Paper No: ICONE25-67232
https://doi.org/10.1115/ICONE25-67232
View Paper titled, Hydraulic Investigations on Free Surface Flow of ADS Windowless Target
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Topics: Flow (Dynamics), Engineering simulation, Pressure, Simulation, Algorithms, Fluids, Heavy metals, Large eddy simulation, Simulation models, Simulation results
Proceedings Papers

Analysis of Fast Reactor Fuel Irradiation Behavior in the MA Recycle System

Takayuki Ozawa
Proc. ASME. ICONE25, Volume 3: Nuclear Fuel and Material, Reactor Physics and Transport Theory; Innovative Nuclear Power Plant Design and New Technology Application, V003T02A006, July 2–6, 2017
Publisher: American Society of Mechanical Engineers
Paper No: ICONE25-66129
https://doi.org/10.1115/ICONE25-66129
View Paper titled, Analysis of Fast Reactor Fuel Irradiation Behavior in the MA Recycle System
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Topics: Fast neutron reactors, Fuels, Irradiation (Radiation exposure), Cladding systems (Building), Temperature, Corrosion, Hazards, Heavy metals, Helium, Melting
Proceedings Papers

Research Progress of Red Oil Explosion Accidents in Nuclear Fuel Reprocessing Plant

Chunlong Zhang, Hui He, Shangui Zhao, Fengli Song, XinHua Liu
Proc. ASME. ICONE25, Volume 7: Fuel Cycle, Decontamination and Decommissioning, Radiation Protection, Shielding, and Waste Management; Mitigation Strategies for Beyond Design Basis Events, V007T10A029, July 2–6, 2017
Publisher: American Society of Mechanical Engineers
Paper No: ICONE25-67554
https://doi.org/10.1115/ICONE25-67554
View Paper titled, Research Progress of Red Oil Explosion Accidents in Nuclear Fuel Reprocessing Plant
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Topics: Accidents, Explosions, Nuclear fuels, Temperature, Safety, Construction, Contamination, Damage, Defense industry, Heavy metals
Proceedings Papers

Conceptual Core Design of Breeding BWR

Rui Guo, Akifumi Yamaji
Proc. ASME. ICONE25, Volume 5: Advanced and Next Generation Reactors, Fusion Technology; Codes, Standards, Conformity Assessment, Licensing, and Regulatory Issues, V005T05A024, July 2–6, 2017
Publisher: American Society of Mechanical Engineers
Paper No: ICONE25-66829
https://doi.org/10.1115/ICONE25-66829
View Paper titled, Conceptual Core Design of Breeding BWR
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Topics: Boiling water reactors, Design, Water, Light water reactors, Fuels, Manufacturing, Neutrons, Atoms, Coolants, Cooling
Proceedings Papers

Electronics for Instrumentation and Controls in Accelerator Driven Sub-Critical System

Wenjuan Cui, Zhiyong He, Qiang Zhao, Yichuan He, Yuxi Luo
Proc. ASME. ICONE24, Volume 1: Operations and Maintenance, Aging Management and Plant Upgrades; Nuclear Fuel, Fuel Cycle, Reactor Physics and Transport Theory; Plant Systems, Structures, Components and Materials; I&C, Digital Controls, and Influence of Human Factors, V001T04A004, June 26–30, 2016
Publisher: American Society of Mechanical Engineers
Paper No: ICONE24-60082
https://doi.org/10.1115/ICONE24-60082
View Paper titled, Electronics for Instrumentation and Controls in Accelerator Driven Sub-Critical System
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Topics: Electronics, Instrumentation, Neutrons, Redundancy (Engineering), Reliability, Errors, Heavy metals, Nuclear industry, Protons, Radiation damage
Proceedings Papers

Preliminary Study on the Feasibility of Utilizing the Thermal Fissile Breeding Capability of the Th-U Fuel Cycle in HTR-PM

Bing Xia, Fu Li
Proc. ASME. ICONE21, Volume 5: Fuel Cycle, Radioactive Waste Management and Decommissioning; Reactor Physics and Transport Theory; Nuclear Education, Public Acceptance and Related Issues; Instrumentation and Controls; Fusion Engineering, V005T08A017, July 29–August 2, 2013
Publisher: American Society of Mechanical Engineers
Paper No: ICONE21-16460
https://doi.org/10.1115/ICONE21-16460
View Paper titled, Preliminary Study on the Feasibility of Utilizing the Thermal Fissile Breeding Capability of the Th-U Fuel Cycle in HTR-PM
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Topics: Nuclear fuel cycle, Fuels, Particulate matter, Uranium, Absorption, Equilibrium (Physics), Heavy metals, High temperature, Safety
Proceedings Papers

Investigation of a Heavy Liquid Metal Free Surface Target Experiment

Karsten Litfin, Frank Fellmoser, Abdalla Batta, Andreas G. Class, Thomas Wetzel
Proc. ASME. ICONE20-POWER2012, Volume 2: Plant Systems, Structures, and Components; Safety and Security; Next Generation Systems; Heat Exchangers and Cooling Systems, 617-623, July 30–August 3, 2012
Publisher: American Society of Mechanical Engineers
Paper No: ICONE20-POWER2012-54460
https://doi.org/10.1115/ICONE20-POWER2012-54460
View Paper titled, Investigation of a Heavy Liquid Metal Free Surface Target Experiment
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Topics: Cavitation, Computational fluid dynamics, Construction, Design, Flow (Dynamics), Fluids, Geometry, Heat, Heavy metals, Imaging
Proceedings Papers

Advanced Recycling Core Accommodating Oxide Fuel and Metal Fuel for Closed Fuel Cycle

Kazumi Ikeda, James W. Maddox, Wataru Nakazato, Shigeru Kunishima
Proc. ASME. ICONE17, Volume 1: Plant Operations, Maintenance, Engineering, Modifications and Life Cycle; Component Reliability and Materials Issues; Next Generation Systems, 873-879, July 12–16, 2009
Publisher: American Society of Mechanical Engineers
Paper No: ICONE17-75499
https://doi.org/10.1115/ICONE17-75499
View Paper titled, Advanced Recycling Core Accommodating Oxide Fuel and Metal Fuel for Closed Fuel Cycle
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Topics: Fuels, Metals, Nuclear fuel cycle, Recycling, Equilibrium (Physics), Combustion, Design, Electric power generation, Heat, Heavy metals
Proceedings Papers

Experimental Study on Natural Circulation and Air-Injection Enhanced Circulation With Different Fluids

W. Ambrosini, N. Forgione, F. Oriolo, E. Semeraro, M. Tarantino
Proc. ASME. ICONE16, Volume 4: Structural Integrity; Next Generation Systems; Safety and Security; Low Level Waste Management and Decommissioning; Near Term Deployment: Plant Designs, Licensing, Construction, Workforce and Public Acceptance, 421-427, May 11–15, 2008
Publisher: American Society of Mechanical Engineers
Paper No: ICONE16-48707
https://doi.org/10.1115/ICONE16-48707
View Paper titled, Experimental Study on Natural Circulation and Air-Injection Enhanced Circulation With Different Fluids
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Topics: Fluids, Water, Cooling, Density, Design, Heavy metals, Scaling laws (Mathematical physics), Thermal expansion
Proceedings Papers

The Effect of the Hydrogen to Heavy Metal Ratio (H/HM) on Reactivity and Discharge Isotopics of Homogeneous Thoria-Urania Fuel

Kevan D. Weaver, J. Stephen Herring
Proc. ASME. ICONE10, 10th International Conference on Nuclear Engineering, Volume 4, 251-257, April 14–18, 2002
Publisher: American Society of Mechanical Engineers
Paper No: ICONE10-22070
https://doi.org/10.1115/ICONE10-22070
View Paper titled, The Effect of the Hydrogen to Heavy Metal Ratio (H/HM) on Reactivity and Discharge Isotopics of Homogeneous Thoria-Urania Fuel
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Topics: Fuels, Heavy metals, Hydrogen, Uranium, Neutrons, Density, Coolants, Hardening, Manufacturing, Nuclear fission
Proceedings Papers

Design of Material Strength Test in Lead-Bismuth Flow

Masatoshi Kondo, Koji Hata, Minoru Takahashi
Proc. ASME. ICONE10, 10th International Conference on Nuclear Engineering, Volume 4, 959-962, April 14–18, 2002
Publisher: American Society of Mechanical Engineers
Paper No: ICONE10-22736
https://doi.org/10.1115/ICONE10-22736
View Paper titled, Design of Material Strength Test in Lead-Bismuth Flow
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Topics: Atomic, molecular, and chemical characteristics, Breeder reactors, Coolants, Design, Flow (Dynamics), Heavy metals, Liquid metals, Strength (Materials)
Proceedings Papers

Technology Perspectives on the Management of Spent-Resin Wastes Generated From Nuclear Power Reactor Operations

Shiv Vijayan, Makoto Kikuchi, Akihiro Komatsu
Proc. ASME. ICONE10, 10th International Conference on Nuclear Engineering, Volume 4, 405-412, April 14–18, 2002
Publisher: American Society of Mechanical Engineers
Paper No: ICONE10-22573
https://doi.org/10.1115/ICONE10-22573
View Paper titled, Technology Perspectives on the Management of Spent-Resin Wastes Generated From Nuclear Power Reactor Operations
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Topics: Nuclear reactors, Resins, Radioisotopes, Storage, Carbon, Half-life, Acceptance criteria, Compacting, Drying, Heavy metals