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Proceedings Papers

Development and Regulatory Reform on Radiation Safety Training for Nuclear Technology Utilization in China

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Yang Zhang, Fangqiang Chen, Baolong Chen, Wei Jia, Zhaotong Li
Proc. ASME. ICONE29, Volume 14: Computer Code Verification and Validation; Nuclear Education and Public Acceptance, V014T15A010, August 8–12, 2022
Publisher: American Society of Mechanical Engineers
Paper No: ICONE29-92435
https://doi.org/10.1115/ICONE29-92435
View Paper titled, Development and Regulatory Reform on Radiation Safety Training for Nuclear Technology Utilization in China
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Topics: China, Radiation (Physics), Regulations, Safety
Proceedings Papers

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

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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

Study on Radioactive Inventory, Accident Source Term and Offsite Dose Consequence of DHR400 Under Fuel Handling Accident and Core Damage Accident

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Fenglong Wang, Xuanlan Mei, Liang Zhang, Yong Yang, Qiang Zhang, Shixi Wang, Mingyu Wu
Proc. ASME. ICONE29, Volume 4: SMRs, Advanced Reactors, and Fusion, V004T04A012, August 8–12, 2022
Publisher: American Society of Mechanical Engineers
Paper No: ICONE29-91511
https://doi.org/10.1115/ICONE29-91511
View Paper titled, Study on Radioactive Inventory, Accident Source Term and Offsite Dose Consequence of DHR400 Under Fuel Handling Accident and Core Damage Accident
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Topics: Accidents, Central heating, Damage, Fuels, China, Design, Background radiation, Emergency management, Hazard analysis, Radioactive substances
Proceedings Papers

Study of the Regular Pattern Between the Geometric Characteristics of Radioactive Package and Its External Radiation Dose Rate

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Zhipeng Wang, Changwu Wang, Qian Sun, Yuhang Zhang, Lei Chen
Proc. ASME. ICONE29, Volume 5: Nuclear Safety, Security, and Cyber Security, V005T05A066, August 8–12, 2022
Publisher: American Society of Mechanical Engineers
Paper No: ICONE29-93641
https://doi.org/10.1115/ICONE29-93641
View Paper titled, Study of the Regular Pattern Between the Geometric Characteristics of Radioactive Package and Its External Radiation Dose Rate
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Topics: Radiation (Physics), Radioactive substances, Safety, Transportation systems, Regulations, Containers, Accidents, Biomedicine, China, Pollution
Proceedings Papers

The Applicability Analysis of Fusion Reactors and China Nuclear Safety Code HAF102

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Yijie Qian, Chong Li
Proc. ASME. ICONE29, Volume 5: Nuclear Safety, Security, and Cyber Security, V005T05A026, August 8–12, 2022
Publisher: American Society of Mechanical Engineers
Paper No: ICONE29-91692
https://doi.org/10.1115/ICONE29-91692
View Paper titled, The Applicability Analysis of Fusion Reactors and China Nuclear Safety Code HAF102
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Topics: China, Fusion reactors, Safety, Design, Defense industry, Nuclear design, Nuclear fission, Nuclear fusion, Nuclear reactors, Regulations
Proceedings Papers

The Research on Common Cause Failure Analysis and Countermeasures for Nuclear Safety Ventilation and Air Conditioning System

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Yongsen Peng, Zhengjie Liu
Proc. ASME. ICONE29, Volume 5: Nuclear Safety, Security, and Cyber Security, V005T05A062, August 8–12, 2022
Publisher: American Society of Mechanical Engineers
Paper No: ICONE29-93557
https://doi.org/10.1115/ICONE29-93557
View Paper titled, The Research on Common Cause Failure Analysis and Countermeasures for Nuclear Safety Ventilation and Air Conditioning System
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Topics: Air conditioning, Countermeasures, Failure, Failure analysis, Safety, Ventilation, Nuclear power stations, Hazard analysis, Regulations, Risk
Proceedings Papers

Simulation of Detection Efficiency of High Integrity Container Gamma Scanning Device for Nuclear Power Plant Based on CZT Detector

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Wenzhang Xie, Jia Huang, Chenyu Shan, Qingxin Lei, Kang Chang, Hao Zhou, Feng Liu, Peng Lin, Xiajie Liu, Li Li
Proc. ASME. ICONE29, Volume 9: Decontamination and Decommissioning, Radiation Protection, and Waste Management, V009T09A012, August 8–12, 2022
Publisher: American Society of Mechanical Engineers
Paper No: ICONE29-91233
https://doi.org/10.1115/ICONE29-91233
View Paper titled, Simulation of Detection Efficiency of High Integrity Container Gamma Scanning Device for Nuclear Power Plant Based on CZT Detector
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Topics: Containers, Nuclear power stations, Sensors, Simulation, Density, Radioactive wastes, Chemical stability, Engineering standards, Evaporation, Filtration
Proceedings Papers

Assessment of Seismic Fragility Using a Three-Dimensional Structural Model of a Reactor Building

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Akemi Nishida, Byunghyun Choi, Tadahiko Shiomi, Manabu Kawata, Yinsheng Li
Proc. ASME. ICONE28, Volume 1: Operating Plant Challenges, Successes, and Lessons Learned; Nuclear Plant Engineering; Advanced Reactors and Fusion; Small Modular and Micro-Reactors Technologies and Applications, V001T02A009, August 4–6, 2021
Publisher: American Society of Mechanical Engineers
Paper No: ICONE28-64300
https://doi.org/10.1115/ICONE28-64300
View Paper titled, Assessment of Seismic Fragility Using a Three-Dimensional Structural Model of a Reactor Building
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Topics: Damage, Design, Earthquakes, Evaluation methods, Failure mechanisms, Hazards, Probabilistic risk assessment, Probability, Regulations, Safety
Proceedings Papers

Finite Element Analysis for Fuel Assembly Structural Behavior

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Youngik Yoo, Kyounghong Kim, Kyongbo Eom, Seongki Lee, Jongsung Yoo
Proc. ASME. ICONE26, Volume 3: Nuclear Fuel and Material, Reactor Physics, and Transport Theory, V003T02A030, July 22–26, 2018
Publisher: American Society of Mechanical Engineers
Paper No: ICONE26-81621
https://doi.org/10.1115/ICONE26-81621
View Paper titled, Finite Element Analysis for Fuel Assembly Structural Behavior
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Topics: Finite element analysis, Fuels, Manufacturing, Accidents, Computer software, Failure mechanisms, Finite element model, Mechanical behavior, Mechanical testing, Radioactive substances
Proceedings Papers

The Role of the NRC in License Renewals

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Samuel Miranda
Proc. ASME. ICONE26, Volume 5: Advanced Reactors and Fusion Technologies; Codes, Standards, Licensing, and Regulatory Issues, V005T07A011, July 22–26, 2018
Publisher: American Society of Mechanical Engineers
Paper No: ICONE26-81904
https://doi.org/10.1115/ICONE26-81904
View Paper titled, The Role of the NRC in License Renewals
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Topics: Licensing, Damage, Design, Fuels, Safety, Acceptance criteria, Health and safety, Regulations
Proceedings Papers

The Backfit Rule’s Compliance Exception

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Samuel Miranda
Proc. ASME. ICONE26, Volume 5: Advanced Reactors and Fusion Technologies; Codes, Standards, Licensing, and Regulatory Issues, V005T07A012, July 22–26, 2018
Publisher: American Society of Mechanical Engineers
Paper No: ICONE26-81905
https://doi.org/10.1115/ICONE26-81905
View Paper titled, The Backfit Rule’s Compliance Exception
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Topics: Accidents, Cost benefit analysis, Errors, Licensing, Platform supply vessels, Regulations, Safety, Valves, Water
Proceedings Papers

Design of the Sampling Measurement and Radiochemistry Lab in the Nuclear Island of HTR-PM

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Mengqi Lou, Wenqian Li, Feng Xie, Jianzhu Cao, Liqiang Wei, Jiejuan Tong, Jiaji Kong
Proc. ASME. ICONE26, Volume 2: Plant Systems, Structures, Components, and Materials; Risk Assessments and Management, V002T03A020, July 22–26, 2018
Publisher: American Society of Mechanical Engineers
Paper No: ICONE26-81701
https://doi.org/10.1115/ICONE26-81701
View Paper titled, Design of the Sampling Measurement and Radiochemistry Lab in the Nuclear Island of HTR-PM
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Topics: Design, Instrumentation, Regulations, Coolants, Dust, Germanium, Helium, Nuclear power stations, Radiation measurement, Radiation measuring instruments
Proceedings Papers

Tests of the Package for the Transport of Natural Uranium Hexafluoride

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Sun Hongchao, Li Guoqiang, Zhuang Dajie, Sun Shutang, Meng Dongyuan, Lian Yiren, Chen Lei, Zhang Jiangang
Proc. ASME. ICONE26, Volume 4: Nuclear Safety, Security, and Cyber Security; Computer Code Verification and Validation, V004T06A034, July 22–26, 2018
Publisher: American Society of Mechanical Engineers
Paper No: ICONE26-82151
https://doi.org/10.1115/ICONE26-82151
View Paper titled, Tests of the Package for the Transport of Natural Uranium Hexafluoride
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Topics: Uranium, External pressure, Finite element analysis, Radioactive substances, Regulations, Structural analysis, Heat, Leakage, Safety, Testing
Proceedings Papers

Classification Optimization for Waste Related Buildings and Structures of NPPs

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Zongwen Hu, Yijie Qian, Li Fan
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, V001T01A004, July 22–26, 2018
Publisher: American Society of Mechanical Engineers
Paper No: ICONE26-81408
https://doi.org/10.1115/ICONE26-81408
View Paper titled, Classification Optimization for Waste Related Buildings and Structures of NPPs
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Topics: Nuclear power stations, Optimization, Structures, Nuclear power, Economics , Radioactive wastes, Regulations
Proceedings Papers

NPP I&C Safety Assessment by Aggregation of Formal Techniques

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Eugene Babeshko, Vyacheslav Kharchenko, Kostiantyn Leontiiev, Oleg Odarushchenko, Oleksiy Strjuk
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, V001T04A016, July 22–26, 2018
Publisher: American Society of Mechanical Engineers
Paper No: ICONE26-82270
https://doi.org/10.1115/ICONE26-82270
View Paper titled, NPP I&C Safety Assessment by Aggregation of Formal Techniques
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Topics: Nuclear power stations, Safety, Computer software, Failure mode and effects analysis, Computers, Control systems, Design, Failure mechanisms, Flow (Dynamics), Hardware
Proceedings Papers

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

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Claude Faidy
Proc. ASME. ICONE26, Volume 5: Advanced Reactors and Fusion Technologies; Codes, Standards, Licensing, and Regulatory Issues, V005T07A002, July 22–26, 2018
Publisher: American Society of Mechanical Engineers
Paper No: ICONE26-81096
https://doi.org/10.1115/ICONE26-81096
View Paper titled, New Needs of Fracture Mechanic Analysis at Design and Operation Level: Status of French Nuclear Mechanical Codes
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Topics: Design, Fracture (Materials), Fracture (Process), Boilers, Brittle fracture, Brittleness, Failure, In-service inspection, Leak-before-break, Manufacturing
Proceedings Papers

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

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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
Publisher: American Society of Mechanical Engineers
Paper No: ICONE26-81436
https://doi.org/10.1115/ICONE26-81436
View Paper titled, Main Evolutions of the RCC-C Design and Construction Code for Fuel Assemblies Since 2015
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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

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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
Publisher: American Society of Mechanical Engineers
Paper No: ICONE26-81893
https://doi.org/10.1115/ICONE26-81893
View Paper titled, AFCEN RCC-F: A New Standard for the Fire Protection Design of New Built Light Water Nuclear Power Plants
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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?

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Samuel Miranda
Proc. ASME. ICONE26, Volume 5: Advanced Reactors and Fusion Technologies; Codes, Standards, Licensing, and Regulatory Issues, V005T07A009, July 22–26, 2018
Publisher: American Society of Mechanical Engineers
Paper No: ICONE26-81901
https://doi.org/10.1115/ICONE26-81901
View Paper titled, What Is a “Known and Established” Standard?
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Topics: Licensing, Regulations
Proceedings Papers

The Design of a Nuclear Emergency Decision Deduction and Training Platform

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Li Ke, Liang Manchun, Su Guofeng, Yang Jie, He Jingtao, He Shuijun
Proc. ASME. ICONE26, Volume 4: Nuclear Safety, Security, and Cyber Security; Computer Code Verification and Validation, V004T06A022, July 22–26, 2018
Publisher: American Society of Mechanical Engineers
Paper No: ICONE26-81691
https://doi.org/10.1115/ICONE26-81691
View Paper titled, The Design of a Nuclear Emergency Decision Deduction and Training Platform
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Topics: Design, Emergencies, Simulation, Accidents, Emergency preparedness, Nuclear power stations, Security, China, Computer simulation, Computer software