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Proceedings Papers

Verification and Validation of JMCT Monte Carlo Code in CPR1000

Proc. ASME. ICONE29, Volume 14: Computer Code Verification and Validation; Nuclear Education and Public Acceptance, V014T14A009, August 8–12, 2022

Paper No: ICONE29-93545

DOI: https://doi.org/10.1115/ICONE29-93545

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Topics: China, Computer technology, Design, Fluence (Radiation measurement), Irradiation (Radiation exposure), Monte Carlo methods, Neutrons, Nuclear engineering, Nuclear power stations, Particulate matter

Proceedings Papers

Study on the Method for the Safety-Related Instrument Calibration Surveillance Interval Extension of Nuclear Power Unit With Analog I&C System Based on Setpoint and Uncertainty Analysis

Yong Zhang, Zhao Zhang, Zi-Chun Wang, Yong-Hui Zhou, Bo-Wen Tang, Min-Hua Su, Wen-Bo Luo

Proc. ASME. ICONE29, Volume 5: Nuclear Safety, Security, and Cyber Security, V005T05A052, August 8–12, 2022

Paper No: ICONE29-92941

DOI: https://doi.org/10.1115/ICONE29-92941

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Topics: Calibration, Instrumentation, Nuclear power, Safety, Surveillance, Uncertainty analysis

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

SCORPIO-VVER: Two Decades of Experience and Enhancements in Reactor Core Monitoring and Surveillance in Central Europe

Jozef Molnar, Marek Pecka, Jaroslav Kment

Proc. ASME. ICONE25, Volume 3: Nuclear Fuel and Material, Reactor Physics and Transport Theory; Innovative Nuclear Power Plant Design and New Technology Application, V003T02A034, July 2–6, 2017

Paper No: ICONE25-66867

DOI: https://doi.org/10.1115/ICONE25-66867

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Topics: Surveillance, Fuels, Construction, Monitoring systems, Nuclear power stations, Computation, Computers, Design, Education, Engineers

Proceedings Papers

Discussion of Tag Gas Method Using in China Experimental Fast Reactor for Failed Fuel Assembly Location

Bie Yewang, Li Huwei, Xiong Wenbin, Zhang Donghui, Wu Mingyu, Wang Xinzhe

Proc. ASME. ICONE25, Volume 2: Plant Systems, Structures, Components and Materials, V002T03A118, July 2–6, 2017

Paper No: ICONE25-67994

DOI: https://doi.org/10.1115/ICONE25-67994

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Topics: China, Fast neutron reactors, Fuels, Manufacturing, Failure, Safety, Cladding systems (Building), Design, Heat transfer, Isotopes

Proceedings Papers

Investigation of Transient Flow and Heat Transfer for Passive Nuclear Reactor Direct Safety Injection

Yu Weng, Lang Liu, Yang Jiang, Hongfang Gu, Haijun Wang

Proc. ASME. NUCLRF2017, ASME 2017 Nuclear Forum, V009T03A003, June 26–30, 2017

Paper No: NUCLRF2017-3452

DOI: https://doi.org/10.1115/NUCLRF2017-3452

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Topics: Heat transfer, Nuclear reactors, Safety, Unsteady flow, Flow (Dynamics), Reactor vessels, Transients (Dynamics), Accidents, Computational fluid dynamics, Nozzles

Proceedings Papers

Intelligent Plant Configuration Management Using Wireless Sensors

Vivek Agarwal, John W. Buttles, Lawrence Beaty, Joseph Naser

Proc. ASME. ICONE24, Volume 1: Operations and Maintenance, Aging Management and Plant Upgrades; Nuclear Fuel, Fuel Cycle, Reactor Physics and Transport Theory; Plant Systems, Structures, Components and Materials; I&C, Digital Controls, and Influence of Human Factors, V001T04A014, June 26–30, 2016

Paper No: ICONE24-60815

DOI: https://doi.org/10.1115/ICONE24-60815

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Topics: Sensors, Nuclear power stations, Safety, Engineering prototypes, Errors, Hazards, Radiation (Physics), Surveillance, Construction, Control systems

Proceedings Papers

Improvement of FAC Maintenance Program Issued From BRT-CICERO™ via CFD Calculations

Elodie Gipon

Proc. ASME. ICONE24, Volume 4: Computational Fluid Dynamics (CFD) and Coupled Codes; Decontamination and Decommissioning, Radiation Protection, Shielding, and Waste Management; Workforce Development, Nuclear Education and Public Acceptance; Mitigation Strategies for Beyond Design Basis Events; Risk Management, V004T10A003, June 26–30, 2016

Paper No: ICONE24-60136

DOI: https://doi.org/10.1115/ICONE24-60136

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Topics: Computational fluid dynamics, Maintenance, Pipes, Computer software, Flow (Dynamics), Nuclear power stations, Algorithms, Corrosion, Feedback, Mass transfer

Proceedings Papers

Implementation of Small Punch Testing and Automated Ball Indentation in the Process of Irradiated NPP Materials Degradation Evaluation

Radim Kopriva, Ivana Eliasova, Milos Kytka

Proc. ASME. ICONE24, Volume 5: Student Paper Competition, V005T15A043, June 26–30, 2016

Paper No: ICONE24-60620

DOI: https://doi.org/10.1115/ICONE24-60620

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Topics: Materials degradation, Nuclear power stations, Testing, Surveillance, Materials properties, Materials testing, Mechanical testing, Testing equipment, Databases, Design

Proceedings Papers

Robust Filtering for Dynamic Compensation of Rhodium Self Powered Neutron Detectors

Xingjie Peng, Kan Wang, Qing Li

Proc. ASME. ICONE22, Volume 6: Nuclear Education, Public Acceptance and Related Issues; Instrumentation and Controls (I&C); Fusion Engineering; Beyond Design Basis Events, V006T13A001, July 7–11, 2014

Paper No: ICONE22-30003

DOI: https://doi.org/10.1115/ICONE22-30003

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Topics: Filtration, Neutrons, Sensors, Neutron flux, Linear matrix inequalities, Noise (Sound), Nuclear reactors, Optimization, Simulation results, Steady state

Proceedings Papers

Loss of Representativeness of the Fixed Incore Instrumentation of the EPR™ Reactor

Brice Jardiné, Olivier Bougeant, Maxime Pfeiffer

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, V001T01A026, July 7–11, 2014

Paper No: ICONE22-31097

DOI: https://doi.org/10.1115/ICONE22-31097

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Topics: Instrumentation, Uncertainty, Surveillance, Probability, Signals, Algorithms, Engineering drawings, Failure, Fuels, Monte Carlo methods

Proceedings Papers

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

Claude Faidy

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

The SCORPIO-VVER Core Monitoring and Surveillance System for VVER Type of Reactors

Jozef Molnar, Radim Vocka

Paper No: ICONE22-30431

DOI: https://doi.org/10.1115/ICONE22-30431

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Topics: Monitoring systems, Nuclear power stations, Design, Fuels, Physicists, Bearings, Education, Neutrons, Physics, Safety

Proceedings Papers

Nodalization of NEK in APROS and Steady State Simulation

Tadeja Polach, Klemen Debelak, Ivica Bašić, Luka Štrubelj

Proc. ASME. ICONE22, Volume 2B: Thermal Hydraulics, V02BT09A026, July 7–11, 2014

Paper No: ICONE22-30869

DOI: https://doi.org/10.1115/ICONE22-30869

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Topics: Simulation, Steady state, Boilers, Nuclear power stations, Circuits, Cycles, Feedwater, Flow (Dynamics), Reactor vessels, Blocks (Building materials)

Proceedings Papers

3D Calculations of PWR Vessels Neutron Fluence With EFLUVE 3D Code

Cécile-Aline Gosmain, Sylvain Rollet, Damien Schmitt

Proc. ASME. ICONE21, Volume 1: Plant Operations, Maintenance, Engineering, Modifications, Life Cycle and Balance of Plant; Nuclear Fuel and Materials; Radiation Protection and Nuclear Technology Applications, V001T02A035, July 29–August 2, 2013

Paper No: ICONE21-16316

DOI: https://doi.org/10.1115/ICONE21-16316

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Topics: Fluence (Radiation measurement), Neutrons, Pressurized water reactors, Vessels, Neutron sources, Surveillance, Chemical kinetics, Pressure vessels, Dosimeters, Dosimetry

Proceedings Papers

Role of Irradiation Embrittlement in RPV Lifetime Assessment

Milan Brumovský, Miloš Kytka

Paper No: ICONE21-15420

DOI: https://doi.org/10.1115/ICONE21-15420

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Topics: Embrittlement, Irradiation (Radiation exposure), Design, Radiation damage, Engineering standards, Failure, Fluence (Radiation measurement), Fracture mechanics, Hardening, Neutron flux

Proceedings Papers

Study on SPMO Management of Contractor Special Process Personnel Qualification Under EPC Mode

Hongwei Shen, Zhiyou Sun, Yang Shen

Paper No: ICONE21-16517

DOI: https://doi.org/10.1115/ICONE21-16517

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Topics: Chain, Construction, Nondestructive evaluation, Nuclear power stations, Painting, Personnel management, Process control, Project management, Quality control, Quality management

Proceedings Papers

RCC-M and RSE-M: A Set of Consistent Codes for PWR Design and Operation

Claude Faidy

Proc. ASME. ICONE21, Volume 3: Nuclear Safety and Security; Codes, Standards, Licensing and Regulatory Issues; Computational Fluid Dynamics and Coupled Codes, V003T07A017, July 29–August 2, 2013

Paper No: ICONE21-16375

DOI: https://doi.org/10.1115/ICONE21-16375

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Topics: Design, Pressurized water reactors, Surveillance, Construction, Inspection, Maintenance, Manufacturing, Nuclear power stations, Welding

Proceedings Papers

Major Improvements of French Mechanical Nuclear Components Codes: RCC-M, RCC-MRx and RSE-M

Claude Faidy

Proc. ASME. ICONE21, Volume 3: Nuclear Safety and Security; Codes, Standards, Licensing and Regulatory Issues; Computational Fluid Dynamics and Coupled Codes, V003T07A018, July 29–August 2, 2013

Paper No: ICONE21-16376

DOI: https://doi.org/10.1115/ICONE21-16376

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Topics: Construction, Design, Fusion reactors, High temperature, Nuclear power stations, Pressure, Pressurized water reactors, Surveillance

Proceedings Papers

EFLUVE3D Code: A 3D Tool for the Neutron Fluence Calculations on Pressurized Water Reactor Vessels

Cécile-Aline Gosmain, Sylvain Rollet, Damien Schmitt

Proc. ASME. ICONE20-POWER2012, Volume 1: Plant Operations, Maintenance, Engineering, Modifications, Life Cycle, and Balance of Plant; Component Reliability and Materials Issues; Steam Generator Technology Applications and Innovations; Advanced Reactors and Near-Term Deployment; Reactor Physics, Neutronics, and Transport Theory; Nuclear Education, Human Resources, and Public Acceptance, 481-489, July 30–August 3, 2012

Paper No: ICONE20-POWER2012-54965

DOI: https://doi.org/10.1115/ICONE20-POWER2012-54965

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Topics: Fluence (Radiation measurement), Neutrons, Pressurized water reactors, Vessels, Neutron sources, Surveillance, Dosimeters, Pressure vessels, Chemical kinetics, Dosimetry

NARROW

Verification and Validation of JMCT Monte Carlo Code in CPR1000

Study on the Method for the Safety-Related Instrument Calibration Surveillance Interval Extension of Nuclear Power Unit With Analog I&C System Based on Setpoint and Uncertainty Analysis

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

SCORPIO-VVER: Two Decades of Experience and Enhancements in Reactor Core Monitoring and Surveillance in Central Europe

Discussion of Tag Gas Method Using in China Experimental Fast Reactor for Failed Fuel Assembly Location

Investigation of Transient Flow and Heat Transfer for Passive Nuclear Reactor Direct Safety Injection

Intelligent Plant Configuration Management Using Wireless Sensors

Improvement of FAC Maintenance Program Issued From BRT-CICERO™ via CFD Calculations

Implementation of Small Punch Testing and Automated Ball Indentation in the Process of Irradiated NPP Materials Degradation Evaluation

Robust Filtering for Dynamic Compensation of Rhodium Self Powered Neutron Detectors

Loss of Representativeness of the Fixed Incore Instrumentation of the EPR™ Reactor

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

The SCORPIO-VVER Core Monitoring and Surveillance System for VVER Type of Reactors

Nodalization of NEK in APROS and Steady State Simulation

3D Calculations of PWR Vessels Neutron Fluence With EFLUVE 3D Code

Role of Irradiation Embrittlement in RPV Lifetime Assessment

Study on SPMO Management of Contractor Special Process Personnel Qualification Under EPC Mode

RCC-M and RSE-M: A Set of Consistent Codes for PWR Design and Operation

Major Improvements of French Mechanical Nuclear Components Codes: RCC-M, RCC-MRx and RSE-M

EFLUVE3D Code: A 3D Tool for the Neutron Fluence Calculations on Pressurized Water Reactor Vessels

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