Topics: Cycles , Earthquake resistant design , Earthquakes , Fatigue , Pipes , Piping systems , Stress , Excitation , ASME Boiler and Pressure Vessel Code , Deformation

Codes Comparative Study on Mechanical Properties of Core Forgings of Reactor Pressure Vessel

Hao Yu, Yinbiao He, Xinxin Wu, Shenjie Gu, Xin Liu, Hongchang Wang

ICONE 2022; V006T06A003https://doi.org/10.1115/ICONE29-90363

Abstract

View Articletitled, Codes Comparative Study on Mechanical Properties of Core Forgings of Reactor Pressure Vessel

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Topics: Forgings (Products) , Mechanical properties , Reactor vessels

Establishment of Engineering Economics Standard System for Nuclear Power Plants in China

Wen Yang, Shaolin Zhang, Jun Huang, Feifei Wu

ICONE 2022; V006T06A004https://doi.org/10.1115/ICONE29-90525

Abstract

View Articletitled, Establishment of Engineering Economics Standard System for Nuclear Power Plants in China

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Topics: China , Engineering economy , Nuclear power stations

The Drafting and Discussion of Terminology of Aging and Life Management for Nuclear Power Plant in China

Zhimin Zhong

ICONE 2022; V006T06A005https://doi.org/10.1115/ICONE29-90645

Abstract

View Articletitled, The Drafting and Discussion of Terminology of Aging and Life Management for Nuclear Power Plant in China

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Topics: China , Engineering drawing and drafting , Nuclear power stations

Research on the Construction of the Advanced Nuclear Power Standards System Platform

Shaolin Zhang, Wen Yang, Ruilin Dong, Yun Liang, Shangyuan Liu

ICONE 2022; V006T06A006https://doi.org/10.1115/ICONE29-91362

Abstract

View Articletitled, Research on the Construction of the Advanced Nuclear Power Standards System Platform

PDF

Topics: Construction , Nuclear power

Analysis of Different Requirements of Dissimilar Metal Joint Welding Procedure Qualification Between RCC-M and ASME BPVC

Wang Pei, Chen Dongxu, Yang Shumin

ICONE 2022; V006T06A007https://doi.org/10.1115/ICONE29-91363

Abstract

View Articletitled, Analysis of Different Requirements of Dissimilar Metal Joint Welding Procedure Qualification Between RCC-M and ASME BPVC

PDF

Topics: ASME Boiler and Pressure Vessel Code , Boilers , Metals , Welding

ISO 19443: Fundamental Requirements of the New Quality Management Standard for the International Nuclear Supply Chain

Jeanne Bargsten, Clemens Treier, Özlem Yilmaz, Amandine Pades, Andrea Kim, Jung-Kyu Lee

ICONE 2022; V006T06A008https://doi.org/10.1115/ICONE29-91803

Abstract

View Articletitled, ISO 19443: Fundamental Requirements of the New Quality Management Standard for the International Nuclear Supply Chain

PDF

Topics: Quality management , Safety , Supply chains

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

Dongyuan Li, Shi Qing, Haiying Luo, Jinkai Wang, Jiaoshen Xu

ICONE 2022; V006T06A009https://doi.org/10.1115/ICONE29-92241

Abstract

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

PDF

Topics: Design , Nuclear design , Risk , Licensing , Safety , Economics , Nuclear power stations , Plant design , Regulations , Self-evaluation

Analysis of Water Consumption in Nuclear Power Plants and National Standard Formulation for Norm of Water Intake

Rui Wang, Kechen Xu, Kehao Zeng, Hongmei Yan, Wei Bai

ICONE 2022; V006T06A010https://doi.org/10.1115/ICONE29-92414

Abstract

View Articletitled, Analysis of Water Consumption in Nuclear Power Plants and National Standard Formulation for Norm of Water Intake

PDF

Topics: Engineering standards , Nuclear power stations , Water

Research on the Practice Qualification System of Registered Nuclear Safety Engineer From the Perspective of Access Professional Qualification

Fangqiang Chen, Yang Zhang, Wei Jia, Zhaotong Li, Guanyi Wang

ICONE 2022; V006T06A011https://doi.org/10.1115/ICONE29-92500

Abstract

View Articletitled, Research on the Practice Qualification System of Registered Nuclear Safety Engineer From the Perspective of Access Professional Qualification

PDF

Topics: Safety engineers

Discussion on Selection of Codes and Standards on Nuclear Power Plant Safety

Chen Yuxiu, Wang Yuhong, Luo Haiying, Wang Jinkai, Shi Qing, Zhu Zengpei, Wu Bei

ICONE 2022; V006T06A012https://doi.org/10.1115/ICONE29-92615

Abstract

View Articletitled, Discussion on Selection of Codes and Standards on Nuclear Power Plant Safety

PDF

Topics: Engineering standards , Nuclear power stations , Safety

Studies on the Principles for Developing In-Service Inspection Acceptance Standards of Reactor Pressure Vessels

Jun Pan, Chang Liu, Xihui Su

ICONE 2022; V006T06A013https://doi.org/10.1115/ICONE29-93037

Abstract

View Articletitled, Studies on the Principles for Developing In-Service Inspection Acceptance Standards of Reactor Pressure Vessels

PDF

Topics: Acceptance criteria , In-service inspection , Reactor vessels , Safety

Practice and Discussion on Safety Categorisation and Classification of Defence in Depth Level 1/2 Functions Based on IAEA-SSG-30

Fan He, Jiangwei Ji, Jiaoshen Xu, Zengpei Zhu, Kewei Cai

ICONE 2022; V006T06A014https://doi.org/10.1115/ICONE29-93238

Abstract

View Articletitled, Practice and Discussion on Safety Categorisation and Classification of Defence in Depth Level 1/2 Functions Based on IAEA-SSG-30

PDF

Topics: Defense industry , Safety

Overview of AFCEN Non-Linear Benchmark in China – Improving Rules for Vessel Ratcheting Evaluation

Yu Tan, Xuejiao Shao, Enming Liang, Shuchun Zuo, Feng Lv, Thomas Metais, Han Liu

ICONE 2022; V006T06A015https://doi.org/10.1115/ICONE29-93561

Abstract

View Articletitled, Overview of AFCEN Non-Linear Benchmark in China – Improving Rules for Vessel Ratcheting Evaluation

PDF

Topics: China , Vessels , Bullets , Computational methods , Computer software , Evaluation methods , Fatigue , Fatigue analysis , Geometry , Nozzles

Comparative Analysis and Research on Nuclear Power Regulation & Standard System and Standardization Works Among China, the U.S. and Japan

Shangyuan Liu, Ran Wei, Shaolin Zhang, Feifei Wu, Jian Du

ICONE 2022; V006T06A016https://doi.org/10.1115/ICONE29-93642

Abstract

View Articletitled, Comparative Analysis and Research on Nuclear Power Regulation & Standard System and Standardization Works Among China, the U.S. and Japan

PDF

Topics: China , Nuclear power

Integration and Future Development of Technical Standards for PWR Nuclear Pressure Equipment

Feifei Wu, Zhenbang Dong, Jun Huang, Shangyuan Liu

ICONE 2022; V006T06A017https://doi.org/10.1115/ICONE29-93746

Abstract

View Articletitled, Integration and Future Development of Technical Standards for PWR Nuclear Pressure Equipment

PDF

Topics: Engineering standards , Pressure equipment , Pressurized water reactors

Analysis and Research of Code Revision for Design of Nuclear Safety Related Concrete Structures of Pressurized Water Reactor Nuclear Power Plants in China

Jun Huang, Weiguo Zhang, Xueyuan Liang, Feifei Wu, Jing Xu, Shaolin Zhang, Wen Yang, Zhiyao Tang

ICONE 2022; V006T06A018https://doi.org/10.1115/ICONE29-93834

Abstract

View Articletitled, Analysis and Research of Code Revision for Design of Nuclear Safety Related Concrete Structures of Pressurized Water Reactor Nuclear Power Plants in China

PDF

Topics: China , Concretes , Design , Nuclear power stations , Pressurized water reactors , Safety

Development of China’s Nuclear Power Standard System and Brief Comparison With American and French Standards

Ruiyuan Deng, Feifei Wu, Zhenbang Dong, Shangyuan Liu, Jian Du, Hongwei Zhang, Yecong Sun, Xueyao Zhang

ICONE 2022; V006T06A019https://doi.org/10.1115/ICONE29-93863

Abstract

View Articletitled, Development of China’s Nuclear Power Standard System and Brief Comparison With American and French Standards

PDF

Topics: Nuclear power

A Step Towards Rules to Identify Bounding Conditions in Terms of Fatigue Damage for NPP Operational Transients

Feng Lv, Zhengyu Zhou, Zhilin Chen, Han Liu, Zihao Zheng

ICONE 2022; V006T06A020https://doi.org/10.1115/ICONE29-94327

Abstract

View Articletitled, A Step Towards Rules to Identify Bounding Conditions in Terms of Fatigue Damage for NPP Operational Transients

PDF

Topics: Fatigue damage , Nuclear power stations , Transients (Dynamics)

All Years

Front Matter

ICONE29 Front Matter

Nuclear Codes, Standards, Licensing, and Regulatory Issues

Effect of the Plasticity of Piping and Support Structures on the Seismic Response of Piping Systems

On Multiaxial Strain Characteristics of Piping Systems Subjected to Earthquake Loads

Codes Comparative Study on Mechanical Properties of Core Forgings of Reactor Pressure Vessel

Establishment of Engineering Economics Standard System for Nuclear Power Plants in China

The Drafting and Discussion of Terminology of Aging and Life Management for Nuclear Power Plant in China

Research on the Construction of the Advanced Nuclear Power Standards System Platform

Analysis of Different Requirements of Dissimilar Metal Joint Welding Procedure Qualification Between RCC-M and ASME BPVC

ISO 19443: Fundamental Requirements of the New Quality Management Standard for the International Nuclear Supply Chain

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

Analysis of Water Consumption in Nuclear Power Plants and National Standard Formulation for Norm of Water Intake

Research on the Practice Qualification System of Registered Nuclear Safety Engineer From the Perspective of Access Professional Qualification

Discussion on Selection of Codes and Standards on Nuclear Power Plant Safety

Studies on the Principles for Developing In-Service Inspection Acceptance Standards of Reactor Pressure Vessels

Practice and Discussion on Safety Categorisation and Classification of Defence in Depth Level 1/2 Functions Based on IAEA-SSG-30

Overview of AFCEN Non-Linear Benchmark in China – Improving Rules for Vessel Ratcheting Evaluation

Comparative Analysis and Research on Nuclear Power Regulation & Standard System and Standardization Works Among China, the U.S. and Japan

Integration and Future Development of Technical Standards for PWR Nuclear Pressure Equipment

Analysis and Research of Code Revision for Design of Nuclear Safety Related Concrete Structures of Pressurized Water Reactor Nuclear Power Plants in China

Development of China’s Nuclear Power Standard System and Brief Comparison With American and French Standards

A Step Towards Rules to Identify Bounding Conditions in Terms of Fatigue Damage for NPP Operational Transients

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