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Proceedings Papers

A Chinese 300MWe Two-Loop PWR NPP LBLOCA Analysis Based on the Deterministic Realistic Hybrid Methodology

Yuhan Li, Bo Kuang
Proc. ASME. ICONE29, Volume 7B: Thermal-Hydraulics and Safety Analysis, V07BT07A009, August 8–12, 2022
Publisher: American Society of Mechanical Engineers
Paper No: ICONE29-92431
https://doi.org/10.1115/ICONE29-92431
View Paper titled, A Chinese 300MWe Two-Loop PWR NPP LBLOCA Analysis Based on the Deterministic Realistic Hybrid Methodology
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Topics: Nuclear power stations, Pressurized water reactors, Safety, Accidents, Life extension, Uncertainty, China, Cladding systems (Building), Coolants, Design
Proceedings Papers

Nuclear Regulatory Acceptance of Certified Process Data Reconciliation (CPDR)

Andy Jansky, Magnus Langenstein
Proc. ASME. ICONE2020, Volume 2: Nuclear Policy; Nuclear Safety, Security, and Cyber Security; Operating Plant Experience; Probabilistic Risk Assessments; SMR and Advanced Reactors, V002T09A006, August 4–5, 2020
Publisher: American Society of Mechanical Engineers
Paper No: ICONE2020-16525
https://doi.org/10.1115/ICONE2020-16525
View Paper titled, Nuclear Regulatory Acceptance of Certified Process Data Reconciliation (CPDR)
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Topics: Maintenance, Measurement uncertainty, Municipal solid wastes, Nuclear power stations, Optimization, Power uprate, Public utilities, Risk, Safety, Solid wastes
Proceedings Papers

Dynamic Simulation Studies of Performed Additional Tests During FAT for Emergency Diesel Generators at Nuclear Power Plant

Salah K. Kanaan, Amer Omanovic
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, V002T05A012, June 26–30, 2016
Publisher: American Society of Mechanical Engineers
Paper No: ICONE24-61084
https://doi.org/10.1115/ICONE24-61084
View Paper titled, Dynamic Simulation Studies of Performed Additional Tests During FAT for Emergency Diesel Generators at Nuclear Power Plant
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Topics: Diesel generators, Emergencies, Nuclear power stations, Simulation, Control equipment, Magnetization, Modeling, Safety, Circuits, Diesel engines
Proceedings Papers

The Role of CHECWORKS™ in an Effective FAC Program

David Smith, Jeffrey Horowitz
Proc. ASME. ICONE22, Volume 1: Plant Operations, Maintenance, Engineering, Modifications, Life Cycle and Balance of Plant; Nuclear Fuel and Materials; Plant Systems, Structures and Components; Codes, Standards, Licensing and Regulatory Issues, V001T01A016, July 7–11, 2014
Publisher: American Society of Mechanical Engineers
Paper No: ICONE22-30854
https://doi.org/10.1115/ICONE22-30854
View Paper titled, The Role of CHECWORKS™ in an Effective FAC Program
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Topics: Accidents, Carbon steel, Computer software, Condensed matter, Corrosion, Engineers, Failure, Flow (Dynamics), Fossil fuels, Inspection
Proceedings Papers

Flow-Induced Vibration Suppression of Jet Pump in Boiling Water Reactor by Slip Joint Extension

Masanobu Watanabe, Kunihiko Kinugasa, Hiroyuki Adachi, Hajime Mori
Proc. ASME. ICONE22, Volume 1: Plant Operations, Maintenance, Engineering, Modifications, Life Cycle and Balance of Plant; Nuclear Fuel and Materials; Plant Systems, Structures and Components; Codes, Standards, Licensing and Regulatory Issues, V001T03A023, July 7–11, 2014
Publisher: American Society of Mechanical Engineers
Paper No: ICONE22-30700
https://doi.org/10.1115/ICONE22-30700
View Paper titled, Flow-Induced Vibration Suppression of Jet Pump in Boiling Water Reactor by Slip Joint Extension
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Topics: Boiling water reactors, Flow-induced vibrations, Jet pumps, Flow (Dynamics), Vibration, Leakage, Damping, Diffusers, Leakage flows, Power uprate
Proceedings Papers

The Load Rejection Transient Analysis of Chinshan NPP (BWR/4) Using TRACE/PARCS

Jhih-Jhong Huang, Hsiung-Chih Chen, Jong-Rong Wang, Lih-Yih Liao, Chunkuan Shih, Hao-Tzu Lin
Proc. ASME. ICONE22, Volume 2B: Thermal Hydraulics, V02BT09A025, July 7–11, 2014
Publisher: American Society of Mechanical Engineers
Paper No: ICONE22-30858
https://doi.org/10.1115/ICONE22-30858
View Paper titled, The Load Rejection Transient Analysis of Chinshan NPP (BWR/4) Using TRACE/PARCS
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Topics: Boiling water reactors, Nuclear power stations, Stress, Transient analysis, Transients (Dynamics), Control systems, Feedwater, Power uprate, Thermal energy, Domes (Structural elements)
Proceedings Papers

Experimental Investigation of Nanotubes Utilization as a Nuclear Fuel Matrix Additive

Jan Varmuza, Karel Katovsky, Jiri Skalicka, Stepan Foral, Jitka Matejkova
Proc. ASME. ICONE22, Volume 5: Innovative Nuclear Power Plant Design and New Technology Application; Student Paper Competition, V005T17A070, July 7–11, 2014
Publisher: American Society of Mechanical Engineers
Paper No: ICONE22-31260
https://doi.org/10.1115/ICONE22-31260
View Paper titled, Experimental Investigation of Nanotubes Utilization as a Nuclear Fuel Matrix Additive
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Topics: Nanotubes, Nuclear fuels, Carbon, Nanomaterials, Neutrons, Aluminum, Cladding systems (Building), Composite materials, Fuels, Materials properties
Proceedings Papers

Hydraulic Lift-Off Issues for Application of High Performance Annular Fuels in Pressurized Water Reactors

Jiyun Zhao, Jingkang Gui
Proc. ASME. ICONE22, Volume 2A: Thermal Hydraulics, V02AT09A043, July 7–11, 2014
Publisher: American Society of Mechanical Engineers
Paper No: ICONE22-30327
https://doi.org/10.1115/ICONE22-30327
View Paper titled, Hydraulic Lift-Off Issues for Application of High Performance Annular Fuels in Pressurized Water Reactors
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Topics: Fuels, Pressurized water reactors, Manufacturing, Design, Coolants, Flow (Dynamics), Cooling, Failure, Power uprate, Steady state
Proceedings Papers

Assessment of APR-1400 Emergency Core Cooling System Performance for Design Basis LOCA Redefinition

Dong Gu Kang, Seung-Hoon Ahn, Soon Heung Chang, Byung-Gil Huh, Young-Seok Bang, Kwang-Won Seul
Proc. ASME. ICONE22, Volume 3: Next Generation Reactors and Advanced Reactors; Nuclear Safety and Security, V003T06A028, July 7–11, 2014
Publisher: American Society of Mechanical Engineers
Paper No: ICONE22-30662
https://doi.org/10.1115/ICONE22-30662
View Paper titled, Assessment of APR-1400 Emergency Core Cooling System Performance for Design Basis LOCA Redefinition
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Topics: Design, Emergency core cooling systems, Accidents, Cooling, Diesel generators, Emergencies, Nuclear power stations, Plant design, Power uprate, Probabilistic safety assessment
Proceedings Papers

Departure From Nucleate Boiling Modeling Development for PWR Fuel

Jin Yan, L. David Smith, III, Zeses Karoutas
Proc. ASME. ICONE21, Volume 3: Nuclear Safety and Security; Codes, Standards, Licensing and Regulatory Issues; Computational Fluid Dynamics and Coupled Codes, V003T10A016, July 29–August 2, 2013
Publisher: American Society of Mechanical Engineers
Paper No: ICONE21-15345
https://doi.org/10.1115/ICONE21-15345
View Paper titled, Departure From Nucleate Boiling Modeling Development for PWR Fuel
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Topics: Fuels, Modeling, Nucleate boiling, Pressurized water reactors, Computational fluid dynamics, Flow (Dynamics), Boiling, Fuel rods, Light water reactors, Accidents
Proceedings Papers

Preliminary Study on the Primary Side Structure Design Improvement Based on CPR1000

Jianshu Lin, Chengjun Zhuang, Jun Cui, Ting Wang, Zhenhua Zhang
Proc. ASME. ICONE21, Volume 3: Nuclear Safety and Security; Codes, Standards, Licensing and Regulatory Issues; Computational Fluid Dynamics and Coupled Codes, V003T06A022, July 29–August 2, 2013
Publisher: American Society of Mechanical Engineers
Paper No: ICONE21-15687
https://doi.org/10.1115/ICONE21-15687
View Paper titled, Preliminary Study on the Primary Side Structure Design Improvement Based on CPR1000
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Topics: Design, Vessels, Fuel rods, Water, Accidents, Nuclear design, Power uprate, Probability, Safety, Temperature
Proceedings Papers

Main Generator Life Cycle Management

Arun Puri, John DiBiase
Proc. ASME. ICONE20-POWER2012, Volume 3: Thermal-Hydraulics; Turbines, Generators, and Auxiliaries, 877-885, July 30–August 3, 2012
Publisher: American Society of Mechanical Engineers
Paper No: ICONE20-POWER2012-55208
https://doi.org/10.1115/ICONE20-POWER2012-55208
View Paper titled, Main Generator Life Cycle Management
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Topics: Generators, Life cycle management, Design, Nuclear power stations, Power uprate, Reliability
Proceedings Papers

Improving Nuclear Power Plant’s Operational Efficiences in the USA

Joseph S. Miller, Bob Stakenborghs, Robert W. Tsai
Proc. ASME. ICONE20-POWER2012, Volume 1: Plant Operations, Maintenance, Engineering, Modifications, Life Cycle, and Balance of Plant; Component Reliability and Materials Issues; Steam Generator Technology Applications and Innovations; Advanced Reactors and Near-Term Deployment; Reactor Physics, Neutronics, and Transport Theory; Nuclear Education, Human Resources, and Public Acceptance, 1-8, July 30–August 3, 2012
Publisher: American Society of Mechanical Engineers
Paper No: ICONE20-POWER2012-54027
https://doi.org/10.1115/ICONE20-POWER2012-54027
View Paper titled, Improving Nuclear Power Plant’s Operational Efficiences in the USA
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Topics: Nuclear power, Nuclear power stations, Fuels, Power stations, Power uprate, Reliability, Safety, Cycles, Electric power generation, Electrical measurement
Proceedings Papers

Feedwater Heater Study for an Extended Power Uprate at a Nuclear Power Station

Eric Svensson, Aravind Krishnamoorthy, Michael Catapano, Michael Coakley, Dan Thomas
Proc. ASME. ICONE20-POWER2012, Volume 1: Plant Operations, Maintenance, Engineering, Modifications, Life Cycle, and Balance of Plant; Component Reliability and Materials Issues; Steam Generator Technology Applications and Innovations; Advanced Reactors and Near-Term Deployment; Reactor Physics, Neutronics, and Transport Theory; Nuclear Education, Human Resources, and Public Acceptance, 197-202, July 30–August 3, 2012
Publisher: American Society of Mechanical Engineers
Paper No: ICONE20-POWER2012-54953
https://doi.org/10.1115/ICONE20-POWER2012-54953
View Paper titled, Feedwater Heater Study for an Extended Power Uprate at a Nuclear Power Station
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Topics: Feedwater, Nuclear power stations, Power uprate, Climate, Computational methods, Cycles, Design, Engineering standards, Failure, Heat
Proceedings Papers

Non-Linear Design Evaluation of Nuclear Power Piping Subjected to Time-History Dynamic Loads According to ASME B&PV III

Lingfu Zeng, Lennart G. Jansson
Proc. ASME. ICONE20-POWER2012, Volume 4: Codes, Standards, Licensing, and Regulatory Issues; Fuel Cycle, Radioactive Waste Management and Decommissioning; Computational Fluid Dynamics (CFD) and Coupled Codes; Instrumentation and Controls; Fuels and Combustion, Materials Handling, Emissions; Advanced Energy Systems and Renewables (Wind, Solar, Geothermal); Performance Testing and Performance Test Codes, 129-138, July 30–August 3, 2012
Publisher: American Society of Mechanical Engineers
Paper No: ICONE20-POWER2012-54484
https://doi.org/10.1115/ICONE20-POWER2012-54484
View Paper titled, Non-Linear Design Evaluation of Nuclear Power Piping Subjected to Time-History Dynamic Loads According to ASME B&PV III
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Topics: Design, Nuclear power, Pipes, Stress, Boiling water reactors, Life extension, Piping systems, Plasticity, Power stations, Power uprate
Proceedings Papers

Optimizing Capacity of Nuclear Power Plants: Thermal Performance Assessment Using a Case Study

Komandur Sunder Raj
Proc. ASME. ICONE20-POWER2012, Volume 1: Plant Operations, Maintenance, Engineering, Modifications, Life Cycle, and Balance of Plant; Component Reliability and Materials Issues; Steam Generator Technology Applications and Innovations; Advanced Reactors and Near-Term Deployment; Reactor Physics, Neutronics, and Transport Theory; Nuclear Education, Human Resources, and Public Acceptance, 91-99, July 30–August 3, 2012
Publisher: American Society of Mechanical Engineers
Paper No: ICONE20-POWER2012-54348
https://doi.org/10.1115/ICONE20-POWER2012-54348
View Paper titled, Optimizing Capacity of Nuclear Power Plants: Thermal Performance Assessment Using a Case Study
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Topics: Corrective actions, Nuclear industry, Nuclear power stations, Optimization, Power uprate, Reliability, Safety, Supply chains
Proceedings Papers

Pressure Drop and Flow Pulsation in Tight-Lattice Rod Bundle

Chi Young Lee, Chang Hwan Shin, Ju Yong Park, Dong Seok Oh, Tae Hyun Chun, Wang Kee In
Proc. ASME. ICONE20-POWER2012, Volume 3: Thermal-Hydraulics; Turbines, Generators, and Auxiliaries, 507-513, July 30–August 3, 2012
Publisher: American Society of Mechanical Engineers
Paper No: ICONE20-POWER2012-54605
https://doi.org/10.1115/ICONE20-POWER2012-54605
View Paper titled, Pressure Drop and Flow Pulsation in Tight-Lattice Rod Bundle
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Topics: Flow (Dynamics), Fuel rods, Pressure drop, Fuels, Manufacturing, Nuclear reactors, Coolants, Pressurized water reactors, Density, Design
Proceedings Papers

How Vertical Project Team Integration Between End User, End User’s Engineer, Nuclear QA, and Equipment Vendor Provided for Minimized Cost and Installation Expense

Jordan Tyman, Joe Bruno, Perry Holzman
Proc. ASME. ICONE20-POWER2012, Volume 2: Plant Systems, Structures, and Components; Safety and Security; Next Generation Systems; Heat Exchangers and Cooling Systems, 805-813, July 30–August 3, 2012
Publisher: American Society of Mechanical Engineers
Paper No: ICONE20-POWER2012-55124
https://doi.org/10.1115/ICONE20-POWER2012-55124
View Paper titled, How Vertical Project Team Integration Between End User, End User’s Engineer, Nuclear QA, and Equipment Vendor Provided for Minimized Cost and Installation Expense
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Topics: Engineers, Teams, Nuclear power stations, Condensed matter, Coolers, Design, Heat exchangers, Lakes, Nozzles, Power stations
Proceedings Papers

On Fatigue Verification of Class 1 Nuclear Power Piping According to ASME NB-3600

Lingfu Zeng, Lennart G. Jansson, Lars Dahlstro¨m
Proc. ASME. ICONE18, 18th International Conference on Nuclear Engineering: Volume 6, 375-383, May 17–21, 2010
Publisher: American Society of Mechanical Engineers
Paper No: ICONE18-29049
https://doi.org/10.1115/ICONE18-29049
View Paper titled, On Fatigue Verification of Class 1 Nuclear Power Piping According to ASME NB-3600
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Topics: Fatigue, Nuclear power, Pipes, Damage, Finite element analysis, Boilers, Boiling water reactors, Computation, Design, Fatigue damage
Proceedings Papers

The Outline of the Five-Percent Power Uprate Project in Tokai-2

Hitoshi Ohata, Toshikazu Nishibata, Tetsuya Onose
Proc. ASME. ICONE18, 18th International Conference on Nuclear Engineering: Volume 1, 295-299, May 17–21, 2010
Publisher: American Society of Mechanical Engineers
Paper No: ICONE18-29845
https://doi.org/10.1115/ICONE18-29845
View Paper titled, The Outline of the Five-Percent Power Uprate Project in Tokai-2
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Topics: Power uprate, Electricity (Physics), Nuclear power stations, Thermal energy, Boiling water reactors, Climate change, Countermeasures, Design, Governments, Licensing