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Proceedings Papers

Enhancement of Shimane Unit 2 Internal Event At-Power PRA for Reflecting New Findings Including Current Plant States

Takahiro Usui, Hiroki Nakamura, Kenichi Ihara, Yuki Hirai, Hitoshi Nojima, Satoshi Yoneda, Kenichi Kanda, Kazunobu Noriyasu, Daichi Shiota, Naoki Hirokawa
Proc. ASME. ICONE31, Volume 10: Risk Assessments and Management; Computer Code Verification and Validation; Nuclear Education and Public Acceptance, V010T12A006, August 4–8, 2024
Publisher: American Society of Mechanical Engineers
Paper No: ICONE31-134400
https://doi.org/10.1115/ICONE31-134400
View Paper titled, Enhancement of Shimane Unit 2 Internal Event At-Power PRA for Reflecting New Findings Including Current Plant States
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Topics: Accidents, Airbags, Boiling water reactors, Design, Electricity (Physics), Engineering standards, Failure data, Fault tree analysis, Fukushima nuclear disaster, Japan, 2011, Human reliability analysis
Proceedings Papers

PSA Application in UK HPR1000 Numerical Targets Evaluation

Lingmei Xiao, Bing Zhang, Ming Wang, Jinkai Wang
Proc. ASME. ICONE29, Volume 13: Risk Assessments and Management, V013T13A038, August 8–12, 2022
Publisher: American Society of Mechanical Engineers
Paper No: ICONE29-92462
https://doi.org/10.1115/ICONE29-92462
View Paper titled, PSA Application in UK HPR1000 Numerical Targets Evaluation
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Topics: Damage, Design, Dimensions, Floods, Nuclear power stations, Plant design, Radiation (Physics), Reactor vessels, Risk, Safety
Proceedings Papers

Application of ALARP Concept in Nuclear Power Plant Design — A Case Study in HPR1000

Dongyuan Li, Shi Qing, Haiying Luo, Jinkai Wang, Jiaoshen Xu
Proc. ASME. ICONE29, Volume 6: Nuclear Codes, Standards, Licensing, and Regulatory Issues, V006T06A009, August 8–12, 2022
Publisher: American Society of Mechanical Engineers
Paper No: ICONE29-92241
https://doi.org/10.1115/ICONE29-92241
View Paper titled, Application of ALARP Concept in Nuclear Power Plant Design — A Case Study in HPR1000
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Topics: Design, Nuclear design, Risk, Licensing, Safety, Economics , Nuclear power stations, Plant design, Regulations, Self-evaluation
Proceedings Papers

Dynamic Modeling of the NSSS Based on NHR200-II Nuclear Heating Reactor

Zhe Dong, Yifei Pan, Miao Liu, Xiaojin Huang
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, V001T13A026, July 22–26, 2018
Publisher: American Society of Mechanical Engineers
Paper No: ICONE26-82579
https://doi.org/10.1115/ICONE26-82579
View Paper titled, Dynamic Modeling of the NSSS Based on NHR200-II Nuclear Heating Reactor
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Topics: Dynamic modeling, Heating, Control systems, Design, Circuits, Coolants, Hardware, Model validation, Momentum, Physics
Proceedings Papers

US Department of Energy’s CoDCon Project: An Aqueous Safeguards R&D Program

James C. Bresee, Patricia D. Paviet, Terry A. Todd
Proc. ASME. ICONE25, Volume 7: Fuel Cycle, Decontamination and Decommissioning, Radiation Protection, Shielding, and Waste Management; Mitigation Strategies for Beyond Design Basis Events, V007T10A047, July 2–6, 2017
Publisher: American Society of Mechanical Engineers
Paper No: ICONE25-67965
https://doi.org/10.1115/ICONE25-67965
View Paper titled, US Department of Energy’s CoDCon Project: An Aqueous Safeguards R&D Program
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Topics: Control systems, Decontamination, Design, Dynamic models, Industrial research, Instrumentation, Nuclear fuels, Nuclear power, Pacific Ocean, Plant design
Proceedings Papers

Strategies to Prevent Benign Transients From Becoming Serious Accidents

Samuel Miranda
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, V002T08A004, June 26–30, 2016
Publisher: American Society of Mechanical Engineers
Paper No: ICONE24-60472
https://doi.org/10.1115/ICONE24-60472
View Paper titled, Strategies to Prevent Benign Transients From Becoming Serious Accidents
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Topics: Accidents, Plant design, Safety, Transients (Dynamics)
Proceedings Papers

Study of the Tank Set of the PRHR on SG Secondary Side

Ran Xu
Proc. ASME. ICONE24, Volume 3: Thermal-Hydraulics, V003T09A061, June 26–30, 2016
Publisher: American Society of Mechanical Engineers
Paper No: ICONE24-60780
https://doi.org/10.1115/ICONE24-60780
View Paper titled, Study of the Tank Set of the PRHR on SG Secondary Side
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Topics: Accidents, Boilers, Design, Heat, Nuclear power stations, Plant design, Safety, Water
Proceedings Papers

Evaluation of Sodium Pool Fire and Thermal Consequence in Two-Cell Configuration

Shuji Ohno, Takashi Takata, Yuji Tajima
Proc. ASME. ICONE24, Volume 3: Thermal-Hydraulics, V003T09A087, June 26–30, 2016
Publisher: American Society of Mechanical Engineers
Paper No: ICONE24-61095
https://doi.org/10.1115/ICONE24-61095
View Paper titled, Evaluation of Sodium Pool Fire and Thermal Consequence in Two-Cell Configuration
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Topics: Liquid pool fires, Sodium, Fire, Combustion, Oxygen, Sodium fast reactors, Aerosols, Computer simulation, Geometry, Heat
Proceedings Papers

3D Linear Bifurcation Analysis of Steel Containment Vessel

Jay Schmidt, Bernd Laskewitz
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, V001T03A018, June 26–30, 2016
Publisher: American Society of Mechanical Engineers
Paper No: ICONE24-60673
https://doi.org/10.1115/ICONE24-60673
View Paper titled, 3D Linear Bifurcation Analysis of Steel Containment Vessel
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Topics: Bifurcation, Containment vessels, Steel, Shells, Stability, Buckling, Containment, Stress, ASME Boiler and Pressure Vessel Code, ASME Standards
Proceedings Papers

Comparison of Fukushima Response in the United States and Europe

Robert J. Lutz, Jr., Robert P. Prior
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, V004T13A004, June 26–30, 2016
Publisher: American Society of Mechanical Engineers
Paper No: ICONE24-60101
https://doi.org/10.1115/ICONE24-60101
View Paper titled, Comparison of Fukushima Response in the United States and Europe
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Topics: Fukushima nuclear disaster, Japan, 2011, Accidents, Stress, Containment, Design, Regulations, Spent nuclear fuels, Accident management, Cooling, Damage
Proceedings Papers

Studies on Maintainability and Repairability for Japan Sodium-Cooled Fast Reactor (JSFR)

Kenichi Isono, Shigenobu Kubo, Yoshitaka Chikazawa, Koji Dozaki, Takeaki Oya, Masahiro Yui
Proc. ASME. ICONE22, Volume 3: Next Generation Reactors and Advanced Reactors; Nuclear Safety and Security, V003T05A007, July 7–11, 2014
Publisher: American Society of Mechanical Engineers
Paper No: ICONE22-30175
https://doi.org/10.1115/ICONE22-30175
View Paper titled, Studies on Maintainability and Repairability for Japan Sodium-Cooled Fast Reactor (JSFR)
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Topics: Coolants, Design, Light water reactors, Maintainability, Maintenance, Plant design, Power stations, Sodium fast reactors
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

AP1000 ® Plant Adaptation To European Markets

Kathyrn J. Demetri, Terry L. Schulz, Bryan N. Friedman
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, V001T01A024, July 7–11, 2014
Publisher: American Society of Mechanical Engineers
Paper No: ICONE22-31057
https://doi.org/10.1115/ICONE22-31057
View Paper titled, AP1000 ® Plant Adaptation To European Markets
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Topics: Accidents, China, Construction, Defense industry, Design, Electricity (Physics), Licensing, Light water reactors, Maintenance, Plant design
Proceedings Papers

AP1000 ® Plant Application of Defense in Depth

Terry L. Schulz, Julie Gorgemans
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, V001T07A014, July 7–11, 2014
Publisher: American Society of Mechanical Engineers
Paper No: ICONE22-31058
https://doi.org/10.1115/ICONE22-31058
View Paper titled, AP1000 ® Plant Application of Defense in Depth
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Topics: Defense industry, Safety, Plant design, Design, Pressurized water reactors, Accidents, Construction, Maintenance, Probabilistic risk assessment
Proceedings Papers

Learning Through Delivery, Westinghouse AP1000® Plant Licensing

Julie Gorgemans, Michael M. Corletti, Richard A. DeLong, Terry L. Schulz
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, V001T07A019, July 7–11, 2014
Publisher: American Society of Mechanical Engineers
Paper No: ICONE22-31204
https://doi.org/10.1115/ICONE22-31204
View Paper titled, Learning Through Delivery, Westinghouse AP1000® Plant Licensing
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Topics: Licensing, Construction, China, Design, Plant design, Pressurized water reactors, Safety, Certainty, Maintenance, Shorelines
Proceedings Papers

Development of Inherently Safe Technologies for Large Scale BWRs: (5) Operation Support System for Plant Accidents

Masaki Kanada, Ryota Kamoshida, Yoshihiko Ishii, Tadaaki Ishikawa, Setsuo Arita, Kenichi Katono
Proc. ASME. ICONE22, Volume 3: Next Generation Reactors and Advanced Reactors; Nuclear Safety and Security, V003T06A049, July 7–11, 2014
Publisher: American Society of Mechanical Engineers
Paper No: ICONE22-31104
https://doi.org/10.1115/ICONE22-31104
View Paper titled, Development of Inherently Safe Technologies for Large Scale BWRs: (5) Operation Support System for Plant Accidents
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Topics: Accidents, Boiling water reactors, Sensors, Signals, Simulation, Errors, Natural disasters, Nuclear reactors, Plant design, Simulation results
Proceedings Papers

Study on Design of Scaled Down Test Facilities for Investigation of Instabilities in Supercritical Water Reactor

Daya Shankar, Dipankar N. Basu, Manmohan Pandey
Proc. ASME. ICONE21, Volume 2: Plant Systems, Construction, Structures and Components; Next Generation Reactors and Advanced Reactors, V002T05A065, July 29–August 2, 2013
Publisher: American Society of Mechanical Engineers
Paper No: ICONE21-16638
https://doi.org/10.1115/ICONE21-16638
View Paper titled, Study on Design of Scaled Down Test Facilities for Investigation of Instabilities in Supercritical Water Reactor
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Topics: Design, Supercritical water reactors, Test facilities, Fluids, Boiling water reactors, High pressure (Physics), Kinematics, Modeling, Plant design, Stability
Proceedings Papers

AP1000 Plant Typical Operational Transient Analysis

Lixin Liu, Limin Zheng
Proc. ASME. ICONE21, Volume 1: Plant Operations, Maintenance, Engineering, Modifications, Life Cycle and Balance of Plant; Nuclear Fuel and Materials; Radiation Protection and Nuclear Technology Applications, V001T01A008, July 29–August 2, 2013
Publisher: American Society of Mechanical Engineers
Paper No: ICONE21-15099
https://doi.org/10.1115/ICONE21-15099
View Paper titled, AP1000 Plant Typical Operational Transient Analysis
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Topics: Computers, Control systems, Design, Light water reactors, Nuclear power stations, Plant design, Power station control systems, Pressurized water reactors, Stress, Transient analysis
Proceedings Papers

LOCA Break Spectrum Analysis of the Westinghouse Small Modular Reactor

Vefa N. Kucukboyaci, Jun Liao
Proc. ASME. ICONE21, Volume 2: Plant Systems, Construction, Structures and Components; Next Generation Reactors and Advanced Reactors, V002T05A075, July 29–August 2, 2013
Publisher: American Society of Mechanical Engineers
Paper No: ICONE21-16884
https://doi.org/10.1115/ICONE21-16884
View Paper titled, LOCA Break Spectrum Analysis of the Westinghouse Small Modular Reactor
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Topics: Emission spectroscopy, Small modular reactors, Spectroscopy, Safety, Design, Pressurized water reactors, Reactor vessels, Accidents, Boilers, Containment
Proceedings Papers

The Feasibility Study of New Design Method for Combined Support of Pipes in Nuclear Engineering

Lang Han, Minjing Tang, Weifeng Jiang
Proc. ASME. ICONE21, Volume 1: Plant Operations, Maintenance, Engineering, Modifications, Life Cycle and Balance of Plant; Nuclear Fuel and Materials; Radiation Protection and Nuclear Technology Applications, V001T01A017, July 29–August 2, 2013
Publisher: American Society of Mechanical Engineers
Paper No: ICONE21-15326
https://doi.org/10.1115/ICONE21-15326
View Paper titled, The Feasibility Study of New Design Method for Combined Support of Pipes in Nuclear Engineering
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Topics: Design methodology, Nuclear engineering, Pipes, Plasma desorption mass spectrometry, Design, Manufacturing, Nuclear power stations, Plant design, Steelwork, Workflow