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Proceedings Papers

Application of Plasma Arc Cutting Technology in Dismantling of Large Metal Components in Containment Building

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Naizhe Zhang, Weishuai Wang, Zhen Gao, Hai Liu, Xuegang Liu
Proc. ASME. ICONE31, Volume 8: Decontamination and Decommissioning, Radiation Protection, and Waste Management, V008T09A017, August 4–8, 2024
Publisher: American Society of Mechanical Engineers
Paper No: ICONE31-135612
https://doi.org/10.1115/ICONE31-135612
View Paper titled, Application of Plasma Arc Cutting Technology in Dismantling of Large Metal Components in Containment Building
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Topics: Containment buildings, Metalwork, Nuclear decommissioning, Nuclear reactors, Plasma arc cutting
Proceedings Papers

AP1000 ® Passive Cooling Containment Analysis of a Double-Ended LBLOCA With a 3D Gothic Model

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Samanta Estevez-Albuja, Gonzalo Jimenez, Kevin Fernández-Cosials, César Queral, Zuriñe Goñi
Proc. ASME. ICONE26, Volume 6B: Thermal-Hydraulics and Safety Analyses, V06BT08A011, July 22–26, 2018
Publisher: American Society of Mechanical Engineers
Paper No: ICONE26-81886
https://doi.org/10.1115/ICONE26-81886
View Paper titled, AP1000 ® Passive Cooling Containment Analysis of a Double-Ended LBLOCA With a 3D Gothic Model
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Topics: Containment, Cooling, Safety, Heat, Pressure, Temperature, Accidents, Alternating current (Electricity), Containment buildings, Containment vessels
Proceedings Papers

Investigation on Fission Products Release Mitigated by In-Containment Relief Valve Under SGTR Accident

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Taeseok Kim, Wonjun Choi, Joongoo Jeon, Nam Kyung Kim, Sung Joong Kim
Proc. ASME. ICONE26, Volume 7: Decontamination and Decommissioning, Radiation Protection, and Waste Management; Mitigation Strategies for Beyond Design Basis Events, V007T11A012, July 22–26, 2018
Publisher: American Society of Mechanical Engineers
Paper No: ICONE26-82161
https://doi.org/10.1115/ICONE26-82161
View Paper titled, Investigation on Fission Products Release Mitigated by In-Containment Relief Valve Under SGTR Accident
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Topics: Accidents, Containment, Nuclear fission, Relief valves, Safety, Nuclides, Boilers, Flow (Dynamics), Valves, Containment buildings
Proceedings Papers

Numerical Simulation of Thermal Hydraulic Phenomena During Spray Injection Using Lagrangian and Eulerian Approaches

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TaeHyub Hong, JongWook Go, MiRo Seo
Proc. ASME. ICONE26, Volume 8: Computational Fluid Dynamics (CFD); Nuclear Education and Public Acceptance, V008T09A020, July 22–26, 2018
Publisher: American Society of Mechanical Engineers
Paper No: ICONE26-81622
https://doi.org/10.1115/ICONE26-81622
View Paper titled, Numerical Simulation of Thermal Hydraulic Phenomena During Spray Injection Using Lagrangian and Eulerian Approaches
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Topics: Computer simulation, Sprays, Drops, Mass transfer, Computational fluid dynamics, Containment buildings, Flow (Dynamics), Heat, Temperature, Pressure
Proceedings Papers

3D Immersive Display Application for Nuclear Education and Public Acceptance

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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
Publisher: American Society of Mechanical Engineers
Paper No: ICONE26-81161
https://doi.org/10.1115/ICONE26-81161
View Paper titled, 3D Immersive Display Application for Nuclear Education and Public Acceptance
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Topics: Education, Nuclear power, Nuclear reactors, Carbon, Containment buildings, Nuclear power stations, Boilers, China, Computer-aided design, Containment
Proceedings Papers

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

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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
Publisher: American Society of Mechanical Engineers
Paper No: ICONE26-82428
https://doi.org/10.1115/ICONE26-82428
View Paper titled, iB1350: Part 1 — A Generation III.7 Reactor iB1350 and Defense in Depth (DiD)
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Topics: Defense industry, Safety, Containment, Containment buildings, Boiling water reactors, Condensers (steam plant), Containment systems, Cooling systems, Design, Domes (Structural elements)
Proceedings Papers

Simulation of Behaviors of a One-Third Scale Containment Model Test

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Guopeng Ren, Rong Pan, Feng Sun
Proc. ASME. ICONE25, Volume 2: Plant Systems, Structures, Components and Materials, V002T03A113, July 2–6, 2017
Publisher: American Society of Mechanical Engineers
Paper No: ICONE25-67779
https://doi.org/10.1115/ICONE25-67779
View Paper titled, Simulation of Behaviors of a One-Third Scale Containment Model Test
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Topics: Containment, Simulation, Tendons, Concretes, Finite element model, Pressure, Deformation, Nuclear power stations, Design, Safety
Proceedings Papers

Numerical Study on Hydrogen Flow Behavior for Different Connecting Pipe Structures

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Hanchen Liu, Kai Yuan, Xuewu Cao
Proc. ASME. ICONE25, Volume 8: Computational Fluid Dynamics (CFD) and Coupled Codes; Nuclear Education, Public Acceptance and Related Issues, V008T09A049, July 2–6, 2017
Publisher: American Society of Mechanical Engineers
Paper No: ICONE25-67375
https://doi.org/10.1115/ICONE25-67375
View Paper titled, Numerical Study on Hydrogen Flow Behavior for Different Connecting Pipe Structures
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Topics: Flow (Dynamics), Hydrogen, Pipes, Computational fluid dynamics, Containment, Vessels, Accidents, Containment buildings, Diffusion (Physics), Engineering simulation
Proceedings Papers

Thermal Hydraulic Performance Analysis for Passive Containment Cooling System of AP1000 in the Event of LOCA

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Talha Bin Mujahid, Yu Yu, Bin Wang, Muhammad Ali Shahzad, Fenglei Niu
Proc. ASME. ICONE25, Volume 6: Thermal-Hydraulics, V006T08A060, July 2–6, 2017
Publisher: American Society of Mechanical Engineers
Paper No: ICONE25-66865
https://doi.org/10.1115/ICONE25-66865
View Paper titled, Thermal Hydraulic Performance Analysis for Passive Containment Cooling System of AP1000 in the Event of LOCA
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Topics: Containment, Cooling systems, Accidents, Safety, Coolants, Design, Pressure, Temperature, Nuclear power stations, Steam
Proceedings Papers

The Application of an Integrated Head Assembly for Advanced Power Reactor 1400

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Tae Kyo Kang, Won Ho Jo, Yeon Ho Cho, Sang Gyoon Chang, Dae Hee Lee
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, V001T01A009, June 26–30, 2016
Publisher: American Society of Mechanical Engineers
Paper No: ICONE24-60860
https://doi.org/10.1115/ICONE24-60860
View Paper titled, The Application of an Integrated Head Assembly for Advanced Power Reactor 1400
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Topics: Manufacturing, Design, Cables, Nuclear power stations, Reactor vessels, China, Containment buildings, Cooling, Ducts, Fans
Proceedings Papers

IRSN R&D Actions on FP Behaviour for RCS, Containment and FCVS in Severe Accident Conditions

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Laurent Cantrel, Thierry Albiol, Loïc Bosland, Juliette Colombani, Frédéric Cousin, Anne-Cécile Grégoire, Olivia Leroy, Sandrine Morin, Christian Mun, Marie-Noël Ohnet, Sidi Souvi, Hugues Vidal, Céline Monsanglant-Louvet, Bruno Azambre, Florent Louis, Christophe Volkringer
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, V004T13A023, June 26–30, 2016
Publisher: American Society of Mechanical Engineers
Paper No: ICONE24-61104
https://doi.org/10.1115/ICONE24-61104
View Paper titled, IRSN R&D Actions on FP Behaviour for RCS, Containment and FCVS in Severe Accident Conditions
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Topics: Accidents, Containment, Chemistry, Filters, Nuclear fission, Porous materials, Collaboration, Computer software, Containment buildings, Fukushima nuclear disaster, Japan, 2011
Proceedings Papers

External Event Risk Assessment: Methodology and Application

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Rosa Lo Frano, Luciano Burgazzi
Proc. ASME. ICONE22, Volume 6: Nuclear Education, Public Acceptance and Related Issues; Instrumentation and Controls (I&C); Fusion Engineering; Beyond Design Basis Events, V006T15A032, July 7–11, 2014
Publisher: American Society of Mechanical Engineers
Paper No: ICONE22-31222
https://doi.org/10.1115/ICONE22-31222
View Paper titled, External Event Risk Assessment: Methodology and Application
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Topics: Risk assessment, Fukushima nuclear disaster, Japan, 2011, Nuclear power stations, Safety, Tsunamis, Accidents, Containment buildings, Earthquakes, Floods, Power stations
Proceedings Papers

Development of a PWR-W and an AP1000 ® Containment Building 3D Model With a CFD Code for Best-Estimate Thermal-Hydraulic Analysis

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Gonzalo Jiménez, Rafael Bocanegra, Kevin Fernández, César Queral, Javier Montero-Mayorga
Proc. ASME. ICONE22, Volume 4: Radiation Protection and Nuclear Technology Applications; Fuel Cycle, Radioactive Waste Management and Decommissioning; Computational Fluid Dynamics (CFD) and Coupled Codes; Reactor Physics and Transport Theory, V004T10A015, July 7–11, 2014
Publisher: American Society of Mechanical Engineers
Paper No: ICONE22-30445
https://doi.org/10.1115/ICONE22-30445
View Paper titled, Development of a PWR-W and an AP1000 ® Containment Building 3D Model With a CFD Code for Best-Estimate Thermal-Hydraulic Analysis
Open the PDF for Development of a PWR-W and an AP1000 ® Containment Building 3D Model With a CFD Code for Best-Estimate Thermal-Hydraulic Analysis in another window
Topics: Computational fluid dynamics, Containment buildings, Pressurized water reactors, Three-dimensional models, Containment, Accidents, Design, Geometry, Licensing, Lumped parameter models
Proceedings Papers

Ventilation Management for the AP1000 Containment Building During Construction Stage

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Zhiyou Sun, Hongwei Shen
Proc. ASME. ICONE21, Volume 2: Plant Systems, Construction, Structures and Components; Next Generation Reactors and Advanced Reactors, V002T03A059, July 29–August 2, 2013
Publisher: American Society of Mechanical Engineers
Paper No: ICONE21-16864
https://doi.org/10.1115/ICONE21-16864
View Paper titled, Ventilation Management for the AP1000 Containment Building During Construction Stage
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Topics: Construction, Containment buildings, Ventilation, Risk, Safety, Accidents, Fume control, Gases, Oxygen
Proceedings Papers

CFD Analysis on Hydrogen Risk in Subcompartment of the Containment

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Zhiqiang Zou, Jian Deng, Yu Zhang
Proc. ASME. ICONE21, Volume 3: Nuclear Safety and Security; Codes, Standards, Licensing and Regulatory Issues; Computational Fluid Dynamics and Coupled Codes, V003T06A038, July 29–August 2, 2013
Publisher: American Society of Mechanical Engineers
Paper No: ICONE21-16171
https://doi.org/10.1115/ICONE21-16171
View Paper titled, CFD Analysis on Hydrogen Risk in Subcompartment of the Containment
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Topics: Computational fluid dynamics, Containment, Hydrogen, Risk, Explosions, Accidents, Boilers, Combustion, Containment buildings, Flames
Proceedings Papers

Evaluation of Damaging Effects on a NPP Integrity Subjected to Beyond Design Earthquake

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Rosa Lo Frano, Giuseppe Forasassi
Proc. ASME. ICONE21, Volume 6: Beyond Design Basis Events; Student Paper Competition, V006T15A018, July 29–August 2, 2013
Publisher: American Society of Mechanical Engineers
Paper No: ICONE21-16469
https://doi.org/10.1115/ICONE21-16469
View Paper titled, Evaluation of Damaging Effects on a NPP Integrity Subjected to Beyond Design Earthquake
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Topics: Design, Earthquakes, Nuclear power stations, Containment, Failure, Bearings, Concretes, Constitutive equations, Containment buildings, Damage
Proceedings Papers

Investigation of Conditions for Zinc Particle Release and Transport in the Reactor Core

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Stefan Renger, Sören Alt, Wolfgang Kästner, André Seeliger, Daniel Fiss
Proc. ASME. ICONE21, Volume 4: Thermal Hydraulics, V004T09A079, July 29–August 2, 2013
Publisher: American Society of Mechanical Engineers
Paper No: ICONE21-16218
https://doi.org/10.1115/ICONE21-16218
View Paper titled, Investigation of Conditions for Zinc Particle Release and Transport in the Reactor Core
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Topics: Accidents, Coolants, Corrosion, Fuels, Particulate matter, Flow (Dynamics), Water, Containment, Fuel rods, Pressurized water reactors
Proceedings Papers

A Comparative Study of Direct Soil Model and Soil Spring Model in Common Basemat Analysis of APR1400 Nuclear Power Plant

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Seong Moon Ahn, Dong Seung Lee, Jae Wan Park, Bhaskar Basu
Proc. ASME. ICONE20-POWER2012, Volume 2: Plant Systems, Structures, and Components; Safety and Security; Next Generation Systems; Heat Exchangers and Cooling Systems, 91-101, July 30–August 3, 2012
Publisher: American Society of Mechanical Engineers
Paper No: ICONE20-POWER2012-54355
https://doi.org/10.1115/ICONE20-POWER2012-54355
View Paper titled, A Comparative Study of Direct Soil Model and Soil Spring Model in Common Basemat Analysis of APR1400 Nuclear Power Plant
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Topics: Nuclear power stations, Soil, Springs, Elastic constants, Containment buildings, Deflection, Iterative methods, Reinforced concrete, Stiffness, Structural analysis
Proceedings Papers

Thermal Hydraulic Analysis of Severe Accident in PFBR

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K. Velusamy, P. Chellapandi, G. R. Raviprasan, P. Selvaraj, S. C. Chetal
Proc. ASME. ICONE18, 18th International Conference on Nuclear Engineering: Volume 4, Parts A and B, 389-399, May 17–21, 2010
Publisher: American Society of Mechanical Engineers
Paper No: ICONE18-29356
https://doi.org/10.1115/ICONE18-29356
View Paper titled, Thermal Hydraulic Analysis of Severe Accident in PFBR
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Topics: Accidents, Pressure, Heat, Sodium, Temperature, Absorption, Accounting, Atmospheric pressure, Breeder reactors, Combustion
Proceedings Papers

Life Extension of the Fast Breeder Test Reactor

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B. Anandapadmanaban, A. Babu, B. Babu, K. Dinesh, V. Ramanathan, G. Srinivasan
Proc. ASME. ICONE18, 18th International Conference on Nuclear Engineering: Volume 1, 97-102, May 17–21, 2010
Publisher: American Society of Mechanical Engineers
Paper No: ICONE18-29277
https://doi.org/10.1115/ICONE18-29277
View Paper titled, Life Extension of the Fast Breeder Test Reactor
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Topics: Life extension, Fuels, Heat, Creep, Cycles, Design, Equipment qualification, Maintenance, Pumps, Safety