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Proceedings Papers

Evaluation of Fatigue Life of Pressurized Water Reactor Internals Considering Light-Water Reactor Coolant Environmental Effect for Aging Management Program

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Jianfeng Yang, Paul O’Brien
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, V001T07A018, July 7–11, 2014
Publisher: American Society of Mechanical Engineers
Paper No: ICONE22-31169
https://doi.org/10.1115/ICONE22-31169
View Paper titled, Evaluation of Fatigue Life of Pressurized Water Reactor Internals Considering Light-Water Reactor Coolant Environmental Effect for Aging Management Program
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Topics: Coolants, Fatigue life, Light water reactors, Pressurized water reactors, Fatigue, Design, Alloys, Cycles, ASME Boiler and Pressure Vessel Code, Carbon
Proceedings Papers

Learning Through Delivery, Westinghouse AP1000® Plant Licensing

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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

Technical Basis of Fatigue Crack Growth Rate Curve for Ni-Base Alloy in BWR Water Environment

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Takuya Ogawa, Masao Itatani, Toshiyuki Saito, Hiroshi Nagase, Satoru Aoike, Hideki Yoneda
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, V001T07A017, July 7–11, 2014
Publisher: American Society of Mechanical Engineers
Paper No: ICONE22-31143
https://doi.org/10.1115/ICONE22-31143
View Paper titled, Technical Basis of Fatigue Crack Growth Rate Curve for Ni-Base Alloy in BWR Water Environment
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Topics: Alloys, Boiling water reactors, Fatigue cracks, Water, Stress, Fitness-for-service, Corrosion, Fracture (Materials), Japan Society of Mechanical Engineers, ASTM International
Proceedings Papers

What is the Relationship Between Quality, Quality Assurance and the Section III Design Specification

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Richard W. Barnes
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, V001T07A020, July 7–11, 2014
Publisher: American Society of Mechanical Engineers
Paper No: ICONE22-31252
https://doi.org/10.1115/ICONE22-31252
View Paper titled, What is the Relationship Between Quality, Quality Assurance and the Section III Design Specification
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Topics: Design, Quality control, Delays, Construction, Quality management
Proceedings Papers

Elaboration of the System Based Code Concept — Activities in JSME and ASME: (3) Guidelines on Structural Reliability Evaluation for FBR

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Shigeru Takaya, Hideo Machida, Yoshio Kamishima
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, V001T07A005, July 7–11, 2014
Publisher: American Society of Mechanical Engineers
Paper No: ICONE22-30570
https://doi.org/10.1115/ICONE22-30570
View Paper titled, Elaboration of the System Based Code Concept — Activities in JSME and ASME: (3) Guidelines on Structural Reliability Evaluation for FBR
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Topics: Japan Society of Mechanical Engineers, Reliability, Failure, Breeder reactors, Crack propagation, Creep, Damage, Fatigue, Modeling, Probability
Proceedings Papers

Elaboration of the System Based Code Concept — Activities in JSME and ASME: (4) Joint Efforts of JSME and ASME

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Tai Asayama, Shigeru Takaya, Masaki Morishita, Frank Schaaf
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, V001T07A006, July 7–11, 2014
Publisher: American Society of Mechanical Engineers
Paper No: ICONE22-30572
https://doi.org/10.1115/ICONE22-30572
View Paper titled, Elaboration of the System Based Code Concept — Activities in JSME and ASME: (4) Joint Efforts of JSME and ASME
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Topics: Japan Society of Mechanical Engineers, ASME Boiler and Pressure Vessel Code, Flow (Dynamics), In-service inspection, Liquid metals, Mechanical engineers, Safety, Sodium fast reactors
Proceedings Papers

A Comparison of Creep-Fatigue Assessment and Modelling Methods

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Rami H. Pohja, Stefan B. Holmström
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, V001T07A007, July 7–11, 2014
Publisher: American Society of Mechanical Engineers
Paper No: ICONE22-30640
https://doi.org/10.1115/ICONE22-30640
View Paper titled, A Comparison of Creep-Fatigue Assessment and Modelling Methods
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Topics: Creep, Fatigue, Modeling, Damage, Design, Cycles, Fatigue damage, Rupture, Steel, Tensile strength
Proceedings Papers

Chinese Innovative Patent Technologies for the Reactor Pressure Vessel

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Qian Shi, Tianqi Zhang, Xiang Fang, Wei Peng
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, V001T07A008, July 7–11, 2014
Publisher: American Society of Mechanical Engineers
Paper No: ICONE22-30694
https://doi.org/10.1115/ICONE22-30694
View Paper titled, Chinese Innovative Patent Technologies for the Reactor Pressure Vessel
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Topics: Patents, Reactor vessels, Nuclear power, China, Design, Safety, Containers, Design methodology, Economics , Innovation
Proceedings Papers

Japanese Codes and Standards for Dual Purpose Metal Casks for Spent Nuclear Fuel

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Toshiari Saegusa, Makoto Hirose, Norikazu Irie, Masashi Shimizu
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, V001T07A009, July 7–11, 2014
Publisher: American Society of Mechanical Engineers
Paper No: ICONE22-30696
https://doi.org/10.1115/ICONE22-30696
View Paper titled, Japanese Codes and Standards for Dual Purpose Metal Casks for Spent Nuclear Fuel
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Topics: Engineering standards, Metals, Spent nuclear fuels, Storage, Stress, Containment vessels, Japan Society of Mechanical Engineers, Safety, Design, Nuclear power stations
Proceedings Papers

Comparison of Nuclear Fitness for Service Codes: ASME Section XI and RSE-M AFCEN Codes

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Claude Faidy
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, V001T07A010, July 7–11, 2014
Publisher: American Society of Mechanical Engineers
Paper No: ICONE22-30713
https://doi.org/10.1115/ICONE22-30713
View Paper titled, Comparison of Nuclear Fitness for Service Codes: ASME Section XI and RSE-M AFCEN Codes
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Topics: Fitness-for-service, In-service inspection, Pressurized water reactors, Light water reactors, Maintenance, Nuclear power stations, Pressure, Surveillance, Boiling, Boiling water reactors
Proceedings Papers

Fatigue Design Rules in Pressure Vessel Codes Uncertainties and Remaining Open Points

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Claude Faidy
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, V001T07A011, July 7–11, 2014
Publisher: American Society of Mechanical Engineers
Paper No: ICONE22-30715
https://doi.org/10.1115/ICONE22-30715
View Paper titled, Fatigue Design Rules in Pressure Vessel Codes Uncertainties and Remaining Open Points
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Topics: Fatigue design, Pressure vessels, Uncertainty, Fatigue, Fatigue analysis, Materials properties, Boilers, Damage, Electromagnetic scattering, Fatigue testing
Proceedings Papers

Comparison of ASME Code NB-3200 and NB-3600-Based Environmental Fatigue Calculations for Piping Components

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Kyeongjin Yang, Daesu Kim, Dongjae Lee, Joonho Lee, Sangbae Lee, Inyeung Kim
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, V001T07A001, July 7–11, 2014
Publisher: American Society of Mechanical Engineers
Paper No: ICONE22-30166
https://doi.org/10.1115/ICONE22-30166
View Paper titled, Comparison of ASME Code NB-3200 and NB-3600-Based Environmental Fatigue Calculations for Piping Components
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Topics: ASME Standards, Fatigue, Pipes, Stress, Light water reactors, Accounting, Coolants, Design, Nuclear power stations, Piping design
Proceedings Papers

Global Materials Research as a Tool for Future Code Development

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Wolfgang Hoffelner
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, V001T07A012, July 7–11, 2014
Publisher: American Society of Mechanical Engineers
Paper No: ICONE22-30969
https://doi.org/10.1115/ICONE22-30969
View Paper titled, Global Materials Research as a Tool for Future Code Development
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Topics: Materials research, Collaboration, Design, Nuclear power stations, Materials properties, Computers, Finite element analysis, Materials degradation, Power stations
Proceedings Papers

Elaboration of the System Based Code Concept — Activities in JSME and ASME: (2) Development of Evaluation Tools Based on LRFD

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Hideo Machida, Tai Asayama, Daigo Watanabe, Kiminobu Hojo, Masaaki Hayashi
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, V001T07A002, July 7–11, 2014
Publisher: American Society of Mechanical Engineers
Paper No: ICONE22-30525
https://doi.org/10.1115/ICONE22-30525
View Paper titled, Elaboration of the System Based Code Concept — Activities in JSME and ASME: (2) Development of Evaluation Tools Based on LRFD
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Topics: Japan Society of Mechanical Engineers, Reliability, Collapse, Design, Bending (Stress), Buckling, Cylinders, Failure, Failure mechanisms, Fatigue
Proceedings Papers

Testing of Statistical Procedures for Use in Optimization of Reactor Performance Under Aged Conditions

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Dumitru Serghiuta, John Tholammakkil, Naj Hammouda, Anthony O’Hagan
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, V001T07A013, July 7–11, 2014
Publisher: American Society of Mechanical Engineers
Paper No: ICONE22-31054
https://doi.org/10.1115/ICONE22-31054
View Paper titled, Testing of Statistical Procedures for Use in Optimization of Reactor Performance Under Aged Conditions
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Topics: Optimization, Testing, Algorithms, Design, Safety, Scalars
Proceedings Papers

Concept of Standard System Based on China Current Nuclear Power Construction

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Yuelan Yan
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, V001T07A003, July 7–11, 2014
Publisher: American Society of Mechanical Engineers
Paper No: ICONE22-30530
https://doi.org/10.1115/ICONE22-30530
View Paper titled, Concept of Standard System Based on China Current Nuclear Power Construction
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Topics: China, Nuclear construction, Nuclear power, Construction, Nuclear power stations, Absorption, ASME Standards, Building codes, Design
Proceedings Papers

AP1000 ® Plant Application of Defense in Depth

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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

Current Implementation of the Quality Assurance Program at the United States Los Alamos National Laboratory

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Taunia Van Valkenburg, Ernie F. Petru, Paula R. Diepolder, Gary M. Sandquist
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, V001T07A015, July 7–11, 2014
Publisher: American Society of Mechanical Engineers
Paper No: ICONE22-31059
https://doi.org/10.1115/ICONE22-31059
View Paper titled, Current Implementation of the Quality Assurance Program at the United States Los Alamos National Laboratory
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Topics: Quality control, Design, Manufacturing, Project management, Risk, Weapons
Proceedings Papers

Elaboration of the System Based Code Concept — Activities in JSME and ASME: (1) Overview

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Tai Asayama, Takayuki Miyagawa, Koji Dozaki, Yoshio Kamishima, Masaaki Hayashi, Hideo Machida
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, V001T07A004, July 7–11, 2014
Publisher: American Society of Mechanical Engineers
Paper No: ICONE22-30567
https://doi.org/10.1115/ICONE22-30567
View Paper titled, Elaboration of the System Based Code Concept — Activities in JSME and ASME: (1) Overview
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Topics: Japan Society of Mechanical Engineers, Reliability, ASME Boiler and Pressure Vessel Code, Collaboration, Design, Engineering standards, In-service inspection, Liquid metals, Mechanical engineers, Sodium fast reactors
Proceedings Papers

Fatigue Assessment of Class 1 Nuclear Power Piping According to ASME BPV Code: Why Other Alternatives?

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Lingfu Zeng, Lennart G. Jansson
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, V001T07A016, July 7–11, 2014
Publisher: American Society of Mechanical Engineers
Paper No: ICONE22-31074
https://doi.org/10.1115/ICONE22-31074
View Paper titled, Fatigue Assessment of Class 1 Nuclear Power Piping According to ASME BPV Code: Why Other Alternatives?
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Topics: Fatigue, Nuclear power, Pipes, Finite element analysis, Stress, ASME Boiler and Pressure Vessel Code, Damage, Design, Reliability