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Proceedings Papers

New Needs of Fracture Mechanic Analysis at Design and Operation Level: Status of French Nuclear Mechanical Codes

Proc. ASME. ICONE26, Volume 5: Advanced Reactors and Fusion Technologies; Codes, Standards, Licensing, and Regulatory Issues, V005T07A002, July 22–26, 2018

Paper No: ICONE26-81096

DOI: https://doi.org/10.1115/ICONE26-81096

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Topics: Design, Fracture (Materials), Fracture (Process), Boilers, Brittle fracture, Brittleness, Failure, In-service inspection, Leak-before-break, Manufacturing

Proceedings Papers

Example of Graded and Lifecycle Phase-Specific Security Controls for Nuclear I&C and EPS Use Cases

Venesa Watson, Edita Bajramovic, Xinxin Lou, Karl Waedt

Proc. ASME. ICONE26, Volume 5: Advanced Reactors and Fusion Technologies; Codes, Standards, Licensing, and Regulatory Issues, V005T07A006, July 22–26, 2018

Paper No: ICONE26-81601

DOI: https://doi.org/10.1115/ICONE26-81601

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Topics: Security, Power stations, Computer security, Computers, Electronic systems, Instrumentation, Maintenance, Nuclear power stations, Programmable controllers, Safety

Proceedings Papers

Establishment of “Technical Guidelines for Watertight Facilities (JEAG4630-2016)”

Koji Yamada, Kyoichi Chuda, Akihiko Masu, Shoichi Goto, Isamu Nakazuka, Yohei Komiyama, Tatsumi Horiuchi, Tomokazu Iwata, Yasuhiro Tsumura, Shizuo Noda

Proc. ASME. ICONE26, Volume 5: Advanced Reactors and Fusion Technologies; Codes, Standards, Licensing, and Regulatory Issues, V005T07A003, July 22–26, 2018

Paper No: ICONE26-81208

DOI: https://doi.org/10.1115/ICONE26-81208

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Topics: Design, Floods, In-service inspection, Nuclear power, Nuclear power stations, Public utilities, Tsunamis

Proceedings Papers

The Quality Experience Feedback in Nuclear Fuel Manufacture

Tong MengYao, Li FangGang

Proc. ASME. ICONE26, Volume 5: Advanced Reactors and Fusion Technologies; Codes, Standards, Licensing, and Regulatory Issues, V005T07A004, July 22–26, 2018

Paper No: ICONE26-81374

DOI: https://doi.org/10.1115/ICONE26-81374

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Topics: Feedback, Nuclear fuels, Manufacturing, Filters, Flow (Dynamics), Fuels, Quality management

Proceedings Papers

Effect of Rolling Motion on Flow Instability of Parallel Rectangular Channels of Natural Circulation

Xiaoyan Wang, Siyang Huang, Wenxi Tian, Lie Chen, Suizheng Qiu, G. H. Su

Proc. ASME. ICONE26, Volume 5: Advanced Reactors and Fusion Technologies; Codes, Standards, Licensing, and Regulatory Issues, V005T07A007, July 22–26, 2018

Paper No: ICONE26-81849

DOI: https://doi.org/10.1115/ICONE26-81849

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Topics: Flow instability, Pressure, Engineering prototypes, FORTRAN, Heating, Simulation, Stability

Proceedings Papers

Main Evolutions of the RCC-C Design and Construction Code for Fuel Assemblies Since 2015

Marc Ton-That, Christine Vauglin, Gilbert Trillon

Proc. ASME. ICONE26, Volume 5: Advanced Reactors and Fusion Technologies; Codes, Standards, Licensing, and Regulatory Issues, V005T07A005, July 22–26, 2018

Paper No: ICONE26-81436

DOI: https://doi.org/10.1115/ICONE26-81436

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Topics: Construction, Design, Fuels, Pressurized water reactors, Manufacturing, Nuclear fuels, Fire, In-service inspection, Inspection, Regulations

Proceedings Papers

AFCEN RCC-F: A New Standard for the Fire Protection Design of New Built Light Water Nuclear Power Plants

Bernard Gautier, Mickael Cesbron, Richard Tulinski

Proc. ASME. ICONE26, Volume 5: Advanced Reactors and Fusion Technologies; Codes, Standards, Licensing, and Regulatory Issues, V005T07A008, July 22–26, 2018

Paper No: ICONE26-81893

DOI: https://doi.org/10.1115/ICONE26-81893

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Topics: Design, Fire, Nuclear power stations, Water, Pressurized water reactors, Hazards, Regulations, Safety, China, Construction

Proceedings Papers

What Is a “Known and Established” Standard?

Samuel Miranda

Proc. ASME. ICONE26, Volume 5: Advanced Reactors and Fusion Technologies; Codes, Standards, Licensing, and Regulatory Issues, V005T07A009, July 22–26, 2018

Paper No: ICONE26-81901

DOI: https://doi.org/10.1115/ICONE26-81901

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Topics: Licensing, Regulations

Proceedings Papers

Nonlinear Analysis in Pressure Vessel Design Codes: Recommendations for Codified Rules Improvements

Claude Faidy

Proc. ASME. ICONE26, Volume 5: Advanced Reactors and Fusion Technologies; Codes, Standards, Licensing, and Regulatory Issues, V005T07A001, July 22–26, 2018

Paper No: ICONE26-81095

DOI: https://doi.org/10.1115/ICONE26-81095

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Topics: Design, Pressure vessels, Stress, Failure mechanisms, Materials properties, Stress analysis (Engineering), Collapse, Constitutive equations, Failure, Fatigue

Proceedings Papers

A Demonstration of Practical Elimination of Early or Large Fission Product Release for the UK ABWR Generic Design Assessment

Ming Leang Ang, Nuh Mohamud, Hiromasa Chitose, Naoki Hirokawa, Ryusuke Kimura

Proc. ASME. ICONE26, Volume 5: Advanced Reactors and Fusion Technologies; Codes, Standards, Licensing, and Regulatory Issues, V005T07A014, July 22–26, 2018

Paper No: ICONE26-82045

DOI: https://doi.org/10.1115/ICONE26-82045

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Topics: Design, Nuclear fission, Safety, Accidents, Nuclear power stations, Construction

Proceedings Papers

Development of a Standard for Fusion Needs: Example of Introduction of Eurofer in RCC-MRx

J. E. Muñoz Garcia, C. Pétesch, T. Lebarbé, P. Lamagnère, Y. Lejeail

Proc. ASME. ICONE26, Volume 5: Advanced Reactors and Fusion Technologies; Codes, Standards, Licensing, and Regulatory Issues, V005T07A018, July 22–26, 2018

Paper No: ICONE26-82337

DOI: https://doi.org/10.1115/ICONE26-82337

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Topics: Construction, Design, Fusion reactors, High temperature, Steel, Vacuum, Vessels

Proceedings Papers

“Begging the Question” in Licensing Basis Accident Analyses

Samuel Miranda

Proc. ASME. ICONE26, Volume 5: Advanced Reactors and Fusion Technologies; Codes, Standards, Licensing, and Regulatory Issues, V005T07A010, July 22–26, 2018

Paper No: ICONE26-81902

DOI: https://doi.org/10.1115/ICONE26-81902

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Topics: Accidents, Licensing, Safety, Damage, Design, Fuels, Nuclear reactor coolants, Pressure, Valves

Proceedings Papers

Discussion on Safety Classification for Equipment of Nuclear Power Plants

He Dan, Zhang Yue

Proc. ASME. ICONE26, Volume 5: Advanced Reactors and Fusion Technologies; Codes, Standards, Licensing, and Regulatory Issues, V005T07A015, July 22–26, 2018

Paper No: ICONE26-82105

DOI: https://doi.org/10.1115/ICONE26-82105

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Topics: Nuclear power stations, Safety, Design, Accidents, Economics , In-service inspection, Maintainability, Nuclear power, Quality control, Reliability

Proceedings Papers

The Role of the NRC in License Renewals

Samuel Miranda

Proc. ASME. ICONE26, Volume 5: Advanced Reactors and Fusion Technologies; Codes, Standards, Licensing, and Regulatory Issues, V005T07A011, July 22–26, 2018

Paper No: ICONE26-81904

DOI: https://doi.org/10.1115/ICONE26-81904

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Topics: Licensing, Damage, Design, Fuels, Safety, Acceptance criteria, Health and safety, Regulations

Proceedings Papers

Study on Supervision Mode of Floating Nuclear Power Plant With Small Modular Reactor

Lei Wan, Guiyong Li, Min Rui, Yongkang Liu, Jue Yang

Proc. ASME. ICONE26, Volume 5: Advanced Reactors and Fusion Technologies; Codes, Standards, Licensing, and Regulatory Issues, V005T07A016, July 22–26, 2018

Paper No: ICONE26-82138

DOI: https://doi.org/10.1115/ICONE26-82138

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Topics: Nuclear power stations, Small modular reactors, Ships, Safety, Construction, Governments, China, Engineering drawings, FPSO, Licensing

Proceedings Papers

The Backfit Rule’s Compliance Exception

Samuel Miranda

Proc. ASME. ICONE26, Volume 5: Advanced Reactors and Fusion Technologies; Codes, Standards, Licensing, and Regulatory Issues, V005T07A012, July 22–26, 2018

Paper No: ICONE26-81905

DOI: https://doi.org/10.1115/ICONE26-81905

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Topics: Accidents, Cost benefit analysis, Errors, Licensing, Platform supply vessels, Regulations, Safety, Valves, Water

Proceedings Papers

Technical Insights of SSR-2/1 Safety of Nuclear Power Plants: Design (Rev.1)

Zheng Hua, Wei Shuhong

Proc. ASME. ICONE26, Volume 5: Advanced Reactors and Fusion Technologies; Codes, Standards, Licensing, and Regulatory Issues, V005T07A013, July 22–26, 2018

Paper No: ICONE26-81983

DOI: https://doi.org/10.1115/ICONE26-81983

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Topics: Design, Nuclear power stations, Safety, Fukushima nuclear disaster, Japan, 2011

Proceedings Papers

ACRS’ Enduring Legacy Contributing to Reactor Safety

Hossein Nourbakhsh

Proc. ASME. ICONE26, Volume 5: Advanced Reactors and Fusion Technologies; Codes, Standards, Licensing, and Regulatory Issues, V005T07A017, July 22–26, 2018

Paper No: ICONE26-82275

DOI: https://doi.org/10.1115/ICONE26-82275

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Topics: Safety

Proceedings Papers

ASME Division 4 Fusion Energy Devices

W. K. Sowder, Richard W. Barnes

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, 1-3, July 30–August 3, 2012

Paper No: ICONE20-POWER2012-54015

DOI: https://doi.org/10.1115/ICONE20-POWER2012-54015

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Topics: Construction, Containment, Design, Engineering standards, Inspection, Manufacturing, Metal stamping, Nonmetallic materials, Pipes, Pumps

Proceedings Papers

Nuclear Safety and Site Evaluation for the Darlington New Nuclear Project

Jack Vecchiarelli, Paul Arthurs, John V. Marczak

Paper No: ICONE20-POWER2012-54874

DOI: https://doi.org/10.1115/ICONE20-POWER2012-54874

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Topics: Safety, Hazards, Risk, Accidents, Design, Earthquake risk, Energy generation, Evacuations, Floods, Governments

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NARROW

New Needs of Fracture Mechanic Analysis at Design and Operation Level: Status of French Nuclear Mechanical Codes

Example of Graded and Lifecycle Phase-Specific Security Controls for Nuclear I&C and EPS Use Cases

Establishment of “Technical Guidelines for Watertight Facilities (JEAG4630-2016)”

The Quality Experience Feedback in Nuclear Fuel Manufacture

Effect of Rolling Motion on Flow Instability of Parallel Rectangular Channels of Natural Circulation

Main Evolutions of the RCC-C Design and Construction Code for Fuel Assemblies Since 2015

AFCEN RCC-F: A New Standard for the Fire Protection Design of New Built Light Water Nuclear Power Plants

What Is a “Known and Established” Standard?

Nonlinear Analysis in Pressure Vessel Design Codes: Recommendations for Codified Rules Improvements

A Demonstration of Practical Elimination of Early or Large Fission Product Release for the UK ABWR Generic Design Assessment

Development of a Standard for Fusion Needs: Example of Introduction of Eurofer in RCC-MRx

“Begging the Question” in Licensing Basis Accident Analyses

Discussion on Safety Classification for Equipment of Nuclear Power Plants

The Role of the NRC in License Renewals

Study on Supervision Mode of Floating Nuclear Power Plant With Small Modular Reactor

The Backfit Rule’s Compliance Exception

Technical Insights of SSR-2/1 Safety of Nuclear Power Plants: Design (Rev.1)

ACRS’ Enduring Legacy Contributing to Reactor Safety

ASME Division 4 Fusion Energy Devices

Nuclear Safety and Site Evaluation for the Darlington New Nuclear Project

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