Search Results | ICONE | ASME Digital Collection

1-20 of 84

2 3 4 5

Sort by

Sort Order Select

Proceedings Papers

Affect Analysis of Surface Liquid Film Coverage on the Safety Performance of Containment

Xingwei Shi, Zhuang Shaoxin, Cui Xinfang, Song Wei, Zuo Jiaxu

Proc. ASME. ICONE28, Volume 1: Operating Plant Challenges, Successes, and Lessons Learned; Nuclear Plant Engineering; Advanced Reactors and Fusion; Small Modular and Micro-Reactors Technologies and Applications, V001T02A008, August 4–6, 2021

Paper No: ICONE28-64278

DOI: https://doi.org/10.1115/ICONE28-64278

View Paper

Topics: Containment, Liquid films, Safety, Scram, Steam

Proceedings Papers

Mixing Characteristic Measurement of Flow in Reactor Pressure Vessel by Laser Induced Fluorescent Method

Mingpeng Chen, Guanhui Xie, Dongyang Li, Sichao Tan

Proc. ASME. ICONE28, Volume 2: Nuclear Fuels, Research, and Fuel Cycle; Nuclear Codes and Standards; Thermal-Hydraulics, V002T07A038, August 4–6, 2021

Paper No: ICONE28-65770

DOI: https://doi.org/10.1115/ICONE28-65770

View Paper

Topics: Boron, Flow measurement, Fluids, Lasers, Reactor vessels, Slug flows, Coolants, Flow (Dynamics), Pressure vessels, Annulus

Proceedings Papers

Code to Code Validation of SAC-3D Based on EBR-II Benchmark Problem

Daogang Lu, Siyu Lyu, Danting Sui

Proc. ASME. ICONE2020, Volume 3: Student Paper Competition; Thermal-Hydraulics; Verification and Validation, V003T14A006, August 4–5, 2020

Paper No: ICONE2020-16666

DOI: https://doi.org/10.1115/ICONE2020-16666

View Paper

Topics: Accidents, Carbon reinforced plastics, China, Electricity (Physics), Fast neutron reactors, Feedback, Flow (Dynamics), Nuclear reactors, Safety, Scram

Proceedings Papers

Severe Accident Analysis for Reactor Core Applying SiC to Fuel Claddings and Channel Boxes

Hideki Horie, Yutaka Takeuchi, Kenya Takiwaki, Fumie Sebe, Kazuo Kakiuchi, Hisaki Sato

Proc. ASME. ICONE26, Volume 3: Nuclear Fuel and Material, Reactor Physics, and Transport Theory, V003T02A034, July 22–26, 2018

Paper No: ICONE26-81923

DOI: https://doi.org/10.1115/ICONE26-81923

View Paper

Topics: Accidents, Fuels, Oxidation, Cladding systems (Building), High temperature, Hydrogen, Nuclear power stations, Temperature, Chemical reactions, Damage

Proceedings Papers

Experimental and Numerical Analysis of the Flow Field in the Integrated Valve for the Control Rod Hydraulic Drive System

Jiang Junfei, Qin Benke, Bo Hanliang

Proc. ASME. ICONE26, Volume 6A: Thermal-Hydraulics and Safety Analyses, V06AT08A028, July 22–26, 2018

Paper No: ICONE26-81305

DOI: https://doi.org/10.1115/ICONE26-81305

View Paper

Topics: Flow (Dynamics), Hydraulic drive systems, Numerical analysis, Valves, Temperature, Design, Computer simulation, Hydraulic cylinders, Computational fluid dynamics, High temperature

Proceedings Papers

Characterization and Experimental Investigation for the Dynamic Performance of the Hydraulically Suspended Passive Shutdown System in China Sodium-Cooled Fast Reactor

Jian Song, Yingwei Wu, Wenxi Tian, Suizheng Qiu, Guanghui Su

Proc. ASME. ICONE26, Volume 9: Student Paper Competition, V009T16A016, July 22–26, 2018

Paper No: ICONE26-81248

DOI: https://doi.org/10.1115/ICONE26-81248

View Paper

Topics: China, Sodium fast reactors, Flow (Dynamics), Pumps, Reliability, Safety, Accidents, Coolants, Design, Engineering prototypes

Proceedings Papers

Validation of a Code and Effect of Turbulence Model on Predicting Thermal Stratification Phenomena in the Upper Plenum of SFR

Shibao Wang, Dalin Zhang, Chenglong Wang, Ping Song, Jing Chen, Suizheng Qiu, Guanghui Su

Proc. ASME. ICONE26, Volume 9: Student Paper Competition, V009T16A035, July 22–26, 2018

Paper No: ICONE26-81551

DOI: https://doi.org/10.1115/ICONE26-81551

View Paper

Topics: Sodium fast reactors, Thermal stratification, Turbulence, Sodium, Momentum, Breeder reactors, Buoyancy, Convection, Deformation, Diffusion (Physics)

Proceedings Papers

3D Immersive Display Application for Nuclear Education and Public Acceptance

Bing Lam Luk, Miu-Ling Lam, Ting-Hsuan Chen, Jiyun Zhao, Suet Man Tsui, Ching-Chang Chieng

Proc. ASME. ICONE26, Volume 8: Computational Fluid Dynamics (CFD); Nuclear Education and Public Acceptance, V008T12A005, July 22–26, 2018

Paper No: ICONE26-81161

DOI: https://doi.org/10.1115/ICONE26-81161

View Paper

Topics: Education, Nuclear power, Nuclear reactors, Carbon, Containment buildings, Nuclear power stations, Boilers, China, Computer-aided design, Containment

Proceedings Papers

Buildup and Decay Analysis of Corrosion Products Activity in Primary Coolant Loop of AP-1000

Fiaz Mahmood, Huasi Hu, Liangzhi Cao

Proc. ASME. ICONE26, Volume 7: Decontamination and Decommissioning, Radiation Protection, and Waste Management; Mitigation Strategies for Beyond Design Basis Events, V007T10A008, July 22–26, 2018

Paper No: ICONE26-81388

DOI: https://doi.org/10.1115/ICONE26-81388

View Paper

Topics: Coolants, Corrosion, Cyber-physical systems, Radiation (Physics), Design, Emergencies, Half-life, Matlab, Neutron flux, Pressurized water reactors

Proceedings Papers

iB1350: Part 1 — A Generation III.7 Reactor iB1350 and Defense in Depth (DiD)

Takashi Sato, Keiji Matsumoto, Kenji Hosomi, Keisuke Taguchi

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, V001T13A023, July 22–26, 2018

Paper No: ICONE26-82428

DOI: https://doi.org/10.1115/ICONE26-82428

View Paper

Topics: Defense industry, Safety, Containment, Containment buildings, Boiling water reactors, Condensers (steam plant), Containment systems, Cooling systems, Design, Domes (Structural elements)

Proceedings Papers

Analysis of Flow Blockage of a Single Fuel Assembly in the JRR-3 20MW Research Reactor

Yuchuan Guo, Guanbo Wang, Dazhi Qian, Heng Yu, Bo Hu

Proc. ASME. ICONE26, Volume 6A: Thermal-Hydraulics and Safety Analyses, V06AT08A030, July 22–26, 2018

Paper No: ICONE26-81313

DOI: https://doi.org/10.1115/ICONE26-81313

View Paper

Topics: Flow (Dynamics), Fuels, Manufacturing, Accidents, Scram, Coolants, Hydraulic drive systems, Nucleate boiling, Plates (structures), Temperature

Proceedings Papers

Numerical Simulation of Safety Rod and its Drive Mechanism in Sodium-Cooled Fast Reactor During Scram Action

Li Yan, Hu Wenjun, Ren Lixia

Proc. ASME. ICONE26, Volume 6A: Thermal-Hydraulics and Safety Analyses, V06AT08A052, July 22–26, 2018

Paper No: ICONE26-81559

DOI: https://doi.org/10.1115/ICONE26-81559

View Paper

Topics: Computer simulation, Safety, Scram, Sodium fast reactors, Accidents, China, Displacement, Fast neutron reactors, Flow (Dynamics), Pipes

Proceedings Papers

The Safety Analysis of Multiple Method Fusion on Reactor Scram Subsystem

Hua Liu, Zhaohui Liu, Xiaohua Yang, Shiyu Yan, Zhi Chen

Proc. ASME. ICONE26, Volume 6B: Thermal-Hydraulics and Safety Analyses, V06BT08A059, July 22–26, 2018

Paper No: ICONE26-82453

DOI: https://doi.org/10.1115/ICONE26-82453

View Paper

Topics: Safety, Scram, Failure mode and effects analysis, Failure, Computer software, Design, Hardware, Accidents, Chain, Complex systems

Proceedings Papers

Development and Basic Verification of Decay Heat Removal Analysis Code of Sodium-Cooled Fast Reactor

Ping Song, Dalin Zhang, Tangtao Feng, Shibao Wang, Yapei Zhang, Mingjun Wang, Suizheng Qiu, G. H. Su

Proc. ASME. ICONE26, Volume 6A: Thermal-Hydraulics and Safety Analyses, V06AT08A061, July 22–26, 2018

Paper No: ICONE26-81630

DOI: https://doi.org/10.1115/ICONE26-81630

View Paper

Topics: Heat, Sodium fast reactors, Accidents, Design, China, Circuits, Errors, Fast neutron reactors, Flow (Dynamics), Generation IV reactors

Proceedings Papers

A PSA Case Study: Promoting the Reliability of the CRSS on the CMRR Through the ATWS Mitigation System

Heng Yu, Guan-bo Wang, Da-zhi Qian, Yu-chuan Guo, Bo Hu

Proc. ASME. ICONE26, Volume 2: Plant Systems, Structures, Components, and Materials; Risk Assessments and Management, V002T14A011, July 22–26, 2018

Paper No: ICONE26-81755

DOI: https://doi.org/10.1115/ICONE26-81755

View Paper

Topics: Reliability, Safety, China, Damage, Design, Failure, Probability, Rods, Scram, Transients (Dynamics)

Proceedings Papers

Numerical and Experimental Analysis of the Control Rod Hydraulic Deceleration Device for the Control Rod Hydraulic Drive System

Qin Benke, Li Leishi, Bo Hanliang

Proc. ASME. ICONE25, Volume 2: Plant Systems, Structures, Components and Materials, V002T03A049, July 2–6, 2017

Paper No: ICONE25-66463

DOI: https://doi.org/10.1115/ICONE25-66463

View Paper

Topics: Experimental analysis, Hydraulic drive systems, Cylinders, Temperature, Flow (Dynamics), Scram, Blades, Design, Dynamics (Mechanics), Fuels

Proceedings Papers

Research of the Rod Drop Time Based on the Control Rod System of TMSR-SF1

Zuokang Lin, Lin Zhu, Chunfeng Zhao, Yun Cao, Xiao Wang

Proc. ASME. ICONE25, Volume 2: Plant Systems, Structures, Components and Materials, V002T03A073, July 2–6, 2017

Paper No: ICONE25-66921

DOI: https://doi.org/10.1115/ICONE25-66921

View Paper

Topics: Accidents, Control systems, Density, Disks, Earthquakes, Errors, Experimental methods, Molten salt reactors, Polishing equipment, Rods

Proceedings Papers

Development of Security and Safety Fuel for Pu-Burner HTGR: Part 3 — Preliminary Reactor Safety Analyses Under Depressurization Accidents

Masaaki Nakano, Kazutaka Ohashi, Koji Okamoto

Proc. ASME. ICONE25, Volume 5: Advanced and Next Generation Reactors, Fusion Technology; Codes, Standards, Conformity Assessment, Licensing, and Regulatory Issues, V005T05A025, July 2–6, 2017

Paper No: ICONE25-66907

DOI: https://doi.org/10.1115/ICONE25-66907

View Paper

Topics: Accidents, Fuels, Safety, Security, Very high temperature reactors, Design, Scram, Uranium, Accident management, Combustion

Proceedings Papers

Thermal-Hydraulic Analysis of the EBR-II SHRT-45R Unprotected Loss of Flow Experiment With Modified RELAP5

Tang Simiao, Song Jian, Zhang Dalin, Wang Chenglong, Qiu Suizheng, Su Guanghui, Tian Wenxi

Proc. ASME. ICONE25, Volume 5: Advanced and Next Generation Reactors, Fusion Technology; Codes, Standards, Conformity Assessment, Licensing, and Regulatory Issues, V005T05A023, July 2–6, 2017

Paper No: ICONE25-66766

DOI: https://doi.org/10.1115/ICONE25-66766

View Paper

Topics: Flow (Dynamics), Sodium fast reactors, Accidents, Feedback, Coolants, Temperature, Fuels, Pumps, Safety, Sodium

Proceedings Papers

Enhancing the Plant’s Capability for Design Extension Conditions Based on Best Estimate Context Evaluation of Human Performance in ATWS Events

Gueorgui Petkov

Proc. ASME. ICONE24, Volume 4: Computational Fluid Dynamics (CFD) and Coupled Codes; Decontamination and Decommissioning, Radiation Protection, Shielding, and Waste Management; Workforce Development, Nuclear Education and Public Acceptance; Mitigation Strategies for Beyond Design Basis Events; Risk Management, V004T13A014, June 26–30, 2016

Paper No: ICONE24-60707

DOI: https://doi.org/10.1115/ICONE24-60707

View Paper

Topics: Design, Accidents, Delays, Dynamics (Mechanics), Engineering simulation, Human factors, Nuclear power stations, Performance evaluation, Pressurized water reactors, Safety

2 3 4 5

NARROW

Affect Analysis of Surface Liquid Film Coverage on the Safety Performance of Containment

Mixing Characteristic Measurement of Flow in Reactor Pressure Vessel by Laser Induced Fluorescent Method

Code to Code Validation of SAC-3D Based on EBR-II Benchmark Problem

Severe Accident Analysis for Reactor Core Applying SiC to Fuel Claddings and Channel Boxes

Experimental and Numerical Analysis of the Flow Field in the Integrated Valve for the Control Rod Hydraulic Drive System

Characterization and Experimental Investigation for the Dynamic Performance of the Hydraulically Suspended Passive Shutdown System in China Sodium-Cooled Fast Reactor

Validation of a Code and Effect of Turbulence Model on Predicting Thermal Stratification Phenomena in the Upper Plenum of SFR

3D Immersive Display Application for Nuclear Education and Public Acceptance

Buildup and Decay Analysis of Corrosion Products Activity in Primary Coolant Loop of AP-1000

iB1350: Part 1 — A Generation III.7 Reactor iB1350 and Defense in Depth (DiD)

Analysis of Flow Blockage of a Single Fuel Assembly in the JRR-3 20MW Research Reactor

Numerical Simulation of Safety Rod and its Drive Mechanism in Sodium-Cooled Fast Reactor During Scram Action

The Safety Analysis of Multiple Method Fusion on Reactor Scram Subsystem

Development and Basic Verification of Decay Heat Removal Analysis Code of Sodium-Cooled Fast Reactor

A PSA Case Study: Promoting the Reliability of the CRSS on the CMRR Through the ATWS Mitigation System

Numerical and Experimental Analysis of the Control Rod Hydraulic Deceleration Device for the Control Rod Hydraulic Drive System

Research of the Rod Drop Time Based on the Control Rod System of TMSR-SF1

Development of Security and Safety Fuel for Pu-Burner HTGR: Part 3 — Preliminary Reactor Safety Analyses Under Depressurization Accidents

Thermal-Hydraulic Analysis of the EBR-II SHRT-45R Unprotected Loss of Flow Experiment With Modified RELAP5

Enhancing the Plant’s Capability for Design Extension Conditions Based on Best Estimate Context Evaluation of Human Performance in ATWS Events

Journals

Conference Proceedings

eBooks

Resources

Opportunities

Journals

Conference Proceedings

eBooks

Resources

Opportunities

This Feature Is Available To Subscribers Only