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Proceedings Papers

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

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
Paper No: ICONE22-30570
DOI: https://doi.org/10.1115/ICONE22-30570
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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

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
Paper No: ICONE22-30572
DOI: https://doi.org/10.1115/ICONE22-30572
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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

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
Paper No: ICONE22-30640
DOI: https://doi.org/10.1115/ICONE22-30640
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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

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
Paper No: ICONE22-30694
DOI: https://doi.org/10.1115/ICONE22-30694
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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

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
Paper No: ICONE22-30696
DOI: https://doi.org/10.1115/ICONE22-30696
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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

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
Paper No: ICONE22-30713
DOI: https://doi.org/10.1115/ICONE22-30713
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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

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
Paper No: ICONE22-30715
DOI: https://doi.org/10.1115/ICONE22-30715
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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

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
Paper No: ICONE22-30166
DOI: https://doi.org/10.1115/ICONE22-30166
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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

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
Paper No: ICONE22-30969
DOI: https://doi.org/10.1115/ICONE22-30969
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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

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
Paper No: ICONE22-30525
DOI: https://doi.org/10.1115/ICONE22-30525
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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

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
Paper No: ICONE22-31054
DOI: https://doi.org/10.1115/ICONE22-31054
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Topics: Optimization, Testing, Algorithms, Design, Safety, Scalars
Proceedings Papers

Concept of Standard System Based on China Current Nuclear Power Construction

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
Paper No: ICONE22-30530
DOI: https://doi.org/10.1115/ICONE22-30530
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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

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
Paper No: ICONE22-31058
DOI: https://doi.org/10.1115/ICONE22-31058
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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

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
Paper No: ICONE22-31059
DOI: https://doi.org/10.1115/ICONE22-31059
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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

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
Paper No: ICONE22-30567
DOI: https://doi.org/10.1115/ICONE22-30567
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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?

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
Paper No: ICONE22-31074
DOI: https://doi.org/10.1115/ICONE22-31074
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Topics: Fatigue, Nuclear power, Pipes, Finite element analysis, Stress, ASME Boiler and Pressure Vessel Code, Damage, Design, Reliability
Proceedings Papers

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

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
Paper No: ICONE22-31143
DOI: https://doi.org/10.1115/ICONE22-31143
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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

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

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
Paper No: ICONE22-31169
DOI: https://doi.org/10.1115/ICONE22-31169
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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

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
Paper No: ICONE22-31204
DOI: https://doi.org/10.1115/ICONE22-31204
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Topics: Licensing, Construction, China, Design, Plant design, Pressurized water reactors, Safety, Certainty, Maintenance, Shorelines
Proceedings Papers

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

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
Paper No: ICONE22-31252
DOI: https://doi.org/10.1115/ICONE22-31252
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Topics: Design, Quality control, Delays, Construction, Quality management