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Proceedings Papers

Neutron Physics Characterization & Optimization Analysis of the ACPR100 Small Modular Reactor

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, V001T04A014, August 4–6, 2021

Paper No: ICONE28-65689

DOI: https://doi.org/10.1115/ICONE28-65689

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Topics: Isotopes, Neutrons, Optimization, Physics, Small modular reactors, Temperature, Cycles, Design, Fuels, China

Proceedings Papers

Research on DTS Analysis Method for 1000MWe PWR NPP

Yubin Zhang

Paper No: ICONE28-64716

DOI: https://doi.org/10.1115/ICONE28-64716

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Topics: Nuclear power stations, Pressurized water reactors

Proceedings Papers

Flux Rate Calculation and Analysis of the Integrated Small Pressurized Water Reactor Based on Monte Carlo Method

Wen Yang, Fei Chao, Yun Tai, Longze Li

Paper No: ICONE28-64448

DOI: https://doi.org/10.1115/ICONE28-64448

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Topics: Monte Carlo methods, Pressurized water reactors

Proceedings Papers

A Finnish District Heating Reactor: Neutronics Design and Fuel Cycle Simulations

Jaakko Leppänen, Ville Valtavirta, Riku Tuominen, Antti Rintala, Unna Lauranto

Paper No: ICONE28-64347

DOI: https://doi.org/10.1115/ICONE28-64347

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Topics: Central heating, Design, Engineering simulation, Nuclear fuel cycle, Simulation, Fuels, Boron, Cycles, Heating, Operating temperature

Proceedings Papers

A Finnish District Heating Reactor: Background and General Overview

Jaakko Leppänen, Seppo Hillberg, Ville Hovi, Rebekka Komu, Joona Kurki, Unna Lauranto, Ahti Oinonen, Jussi Peltonen, Antti Rintala, Ville Tulkki, Riku Tuominen, Ville Valtavirta

Paper No: ICONE28-64346

DOI: https://doi.org/10.1115/ICONE28-64346

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Topics: Central heating, Design, Coal, Governments, Heat, Boilers, Carbon, Climate, Containment, Energy generation

Proceedings Papers

Codes and Methods Improvements for VVER Comprehensive Safety Assessment: The CAMIVVER H2020 Project

Proc. ASME. ICONE28, Volume 2: Nuclear Fuels, Research, and Fuel Cycle; Nuclear Codes and Standards; Thermal-Hydraulics, V002T07A010, August 4–6, 2021

Paper No: ICONE28-64169

DOI: https://doi.org/10.1115/ICONE28-64169

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Topics: Physics, Pressurized water reactors, Safety, Computers, Computational fluid dynamics, Maintenance, Modeling, Nuclear industry, Security, Thermal hydraulics

Proceedings Papers

RELAP5 Code Analyses of PKL-4 Project Test on PWR Multiple Steam Generator Tube Rupture Accident With Recovery Actions

Masashi Sekine, Junichi Kaneko, Takeshi Takeda

Proc. ASME. ICONE28, Volume 2: Nuclear Fuels, Research, and Fuel Cycle; Nuclear Codes and Standards; Thermal-Hydraulics, V002T07A009, August 4–6, 2021

Paper No: ICONE28-64117

DOI: https://doi.org/10.1115/ICONE28-64117

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Topics: Accidents, Boilers, Pressurized water reactors, Rupture, Damage, Cooling, Earthquakes, Emergency core cooling systems, Failure, Feedwater

Proceedings Papers

Development of Digital Twins of PWR Steam Generators: Description of Two Maintenance-Oriented Use Cases

Enrico Deri, Christophe Varé, Matthieu Wintergerst

Paper No: ICONE28-63246

DOI: https://doi.org/10.1115/ICONE28-63246

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Topics: Boilers, Maintenance, Pressurized water reactors, Computation, Design, Emergency preparedness, Engineering disciplines, Fracture (Materials), Inspection, Instrumentation

Proceedings Papers

Baseline WALT DNB Test Results With Cr-Coated Cladding to Support Accident Tolerant Fuel Development

Guoqiang Wang, William A. Byers, Zeses Karoutas

Proc. ASME. ICONE28, Volume 2: Nuclear Fuels, Research, and Fuel Cycle; Nuclear Codes and Standards; Thermal-Hydraulics, V002T07A041, August 4–6, 2021

Paper No: ICONE28-66591

DOI: https://doi.org/10.1115/ICONE28-66591

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Topics: Accidents, Cladding systems (Building), Critical heat flux, Fuels, Chemistry, Pressurized water reactors, Coolants, Electrical resistivity, Film boiling, Heat flux

Proceedings Papers

Flow Induced Vibration and Fretting Wear Characteristics of Fuel Rods

Zhipeng Feng, Huanhuan Qi, Xuan Huang, Guo Chen, Shuai Liu, Yixiong Zhang

Proc. ASME. ICONE28, Volume 2: Nuclear Fuels, Research, and Fuel Cycle; Nuclear Codes and Standards; Thermal-Hydraulics, V002T05A003, August 4–6, 2021

Paper No: ICONE28-62135

DOI: https://doi.org/10.1115/ICONE28-62135

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Topics: Flow-induced vibrations, Fuel rods, Wear, Fuels, Manufacturing, Design, Fluid density, Pressurized water reactors, Evaluation methods, Excitation

Proceedings Papers

Dynamic Characteristics Analysis of NuScale in Frequency Domain

Jingrui Yang, Qian Ma, Lingtong Han, Peiwei Sun

Paper No: ICONE28-64460

DOI: https://doi.org/10.1115/ICONE28-64460

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Topics: Boilers, Coolants, Design, Electric power generation, Feedwater, Flow (Dynamics), Frequency-domain analysis, Heating, Momentum, Neutrons

Proceedings Papers

Mixing Characteristic Measurement of Flow in Reactor Pressure Vessel by Laser Induced Fluorescent Method

Mingpeng Chen, Guanhui Xie, Dongyang Li, Sichao Tan

Proc. ASME. ICONE28, Volume 2: Nuclear Fuels, Research, and Fuel Cycle; Nuclear Codes and Standards; Thermal-Hydraulics, V002T07A038, August 4–6, 2021

Paper No: ICONE28-65770

DOI: https://doi.org/10.1115/ICONE28-65770

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Topics: Boron, Flow measurement, Fluids, Lasers, Reactor vessels, Slug flows, Coolants, Flow (Dynamics), Pressure vessels, Annulus

Proceedings Papers

Study on the Small Pressurized Water Reactor Based on Fully Ceramic Microencapsulated Fuel

Jin Feng Huang

Paper No: ICONE28-63314

DOI: https://doi.org/10.1115/ICONE28-63314

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Topics: Ceramics, Fuels, Pressurized water reactors, Cladding systems (Building), Cycles, Nuclear power stations, Silicon, Temperature, Thermal conductivity, Boron

Proceedings Papers

Prediction of Iodine Peak and Iodine Purification Time in PWR Nuclear Power Plant With Defective Fuel Rods

Liang Wang, Zhiyuan Liu, Fei Liu, Chunming Zhang, Fudong Liu, Yuanlv Ye

Proc. ASME. ICONE28, Volume 2: Nuclear Fuels, Research, and Fuel Cycle; Nuclear Codes and Standards; Thermal-Hydraulics, V002T05A007, August 4–6, 2021

Paper No: ICONE28-64147

DOI: https://doi.org/10.1115/ICONE28-64147

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Topics: Failure, Fuel rods, Nuclear power stations, Pressurized water reactors, Radiation (Physics), Safety

Proceedings Papers

Hydrodynamic Analysis of Steam Generator Under LOCA Conditions

Xiaoqiang He, Puzhen Gao, Weichao Yuan

Proc. ASME. ICONE28, Volume 3: Computational Fluid Dynamics (CFD); Verification and Validation; Advanced Methods of Manufacturing (AMM) for Nuclear Reactors and Components; Decontamination, Decommissioning, and Radioactive Waste Management; Beyond Design Basis and Nuclear Safety; Risk Informed Management and Regulation, V003T12A030, August 4–6, 2021

Paper No: ICONE28-64709

DOI: https://doi.org/10.1115/ICONE28-64709

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Topics: Boilers, Fluid-dynamic forces, Pressure, Accidents, Nuclear power stations, Coolants, Design, Flow (Dynamics), Fluids, Nozzles

Proceedings Papers

Linear Active Disturbance Rejection Control of Steam Bypass System for a Pressurized Water Reactor

Xianshan Zhang, Peiwei Sun, Xinyu Wei, Xiaolong Gou, Guocheng Tan, Yajie Tian

Proc. ASME. ICONE28, Volume 4: Student Paper Competition, V004T14A037, August 4–6, 2021

Paper No: ICONE28-64451

DOI: https://doi.org/10.1115/ICONE28-64451

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Topics: Flow (Dynamics), Pressurized water reactors, Steam

Proceedings Papers

Verification of PWR-Core Analysis Code CORAL Using VERA Core Physics Benchmark

Wen Yang, Fei Chao, Jinrong Qiu, Xing Li, Baolin Liu

Paper No: ICONE28-64721

DOI: https://doi.org/10.1115/ICONE28-64721

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Topics: Physics, Pressurized water reactors

Proceedings Papers

Study on Radiation Dose Calculation of PWR Spent Fuel Storage and Transportation

Wen Yang, Xing Li, Jinrong Qiu, Lun Zhou

Proc. ASME. ICONE28, Volume 4: Student Paper Competition, V004T14A042, August 4–6, 2021

Paper No: ICONE28-64457

DOI: https://doi.org/10.1115/ICONE28-64457

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Topics: Containers, Pressurized water reactors, Radiation (Physics), Spent fuel storage, Spent nuclear fuels, Transportation systems

Proceedings Papers

Level 2 Probability Safety Assessment for External Events: Approach and Application for NPPs in China

Yu Liu, Cong Wang, Jing Liu, Heng Gao

Paper No: ICONE28-64329

DOI: https://doi.org/10.1115/ICONE28-64329

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Topics: China, Nuclear power stations, Probability, Safety, Computer software, Fukushima nuclear disaster, Japan, 2011, Pressurized water reactors, Radioactive substances, Risk, Tsunamis

Proceedings Papers

Resistance and Thermal Stress Analysis of Mini-Flow Pipeline of Residual Heat Removal System in Pressurized Water Reactor

Yue Pi, Ting Hou

Paper No: ICONE28-64401

DOI: https://doi.org/10.1115/ICONE28-64401

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Topics: Flow (Dynamics), Fluids, Heat, Pipelines, Pressurized water reactors, Thermal stresses

2 3 4 5

NARROW

Neutron Physics Characterization & Optimization Analysis of the ACPR100 Small Modular Reactor

Research on DTS Analysis Method for 1000MWe PWR NPP

Flux Rate Calculation and Analysis of the Integrated Small Pressurized Water Reactor Based on Monte Carlo Method

A Finnish District Heating Reactor: Neutronics Design and Fuel Cycle Simulations

A Finnish District Heating Reactor: Background and General Overview

Codes and Methods Improvements for VVER Comprehensive Safety Assessment: The CAMIVVER H2020 Project

RELAP5 Code Analyses of PKL-4 Project Test on PWR Multiple Steam Generator Tube Rupture Accident With Recovery Actions

Development of Digital Twins of PWR Steam Generators: Description of Two Maintenance-Oriented Use Cases

Baseline WALT DNB Test Results With Cr-Coated Cladding to Support Accident Tolerant Fuel Development

Flow Induced Vibration and Fretting Wear Characteristics of Fuel Rods

Dynamic Characteristics Analysis of NuScale in Frequency Domain

Mixing Characteristic Measurement of Flow in Reactor Pressure Vessel by Laser Induced Fluorescent Method

Study on the Small Pressurized Water Reactor Based on Fully Ceramic Microencapsulated Fuel

Prediction of Iodine Peak and Iodine Purification Time in PWR Nuclear Power Plant With Defective Fuel Rods

Hydrodynamic Analysis of Steam Generator Under LOCA Conditions

Linear Active Disturbance Rejection Control of Steam Bypass System for a Pressurized Water Reactor

Verification of PWR-Core Analysis Code CORAL Using VERA Core Physics Benchmark

Study on Radiation Dose Calculation of PWR Spent Fuel Storage and Transportation

Level 2 Probability Safety Assessment for External Events: Approach and Application for NPPs in China

Resistance and Thermal Stress Analysis of Mini-Flow Pipeline of Residual Heat Removal System in Pressurized Water Reactor

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