Search Results | ICONE | ASME Digital Collection

1-20 of 471

2 3 4 5

Sort by

Sort Order Select

Proceedings Papers

Thermal Hydraulics Analysis of a High-Performance Once-Through Steam Generator With Annular Narrow Slot Tube

Jinyu Han, Wen He, Shunran Guan, Chenru Zhao, Hanliang Bo

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, V001T04A007, August 4–6, 2021

Paper No: ICONE28-64168

DOI: https://doi.org/10.1115/ICONE28-64168

View Paper

Topics: Boilers, Thermal hydraulics

Proceedings Papers

A High-Temperature Gas-Cooled Reactor Simulation System and Its Application Based on VPOWER Platform

Biheng Xie, Chengzhi Ji, Xiaoyu Guo, Wenbin Han, Yisheng Hao, Junyi Chen, Shanfang Huang, Kan Wang, Hongbin Wei, Yanming Liang

Paper No: ICONE28-64532

DOI: https://doi.org/10.1115/ICONE28-64532

View Paper

Topics: Simulation, Teaching, Very high temperature reactors, Accidents, Nuclear engineering, Nuclear industry, Students, Boilers, Control systems, Design

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

View Paper

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

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

View Paper

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

View Paper

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

Proceedings Papers

Numerical Evaluation of Sodium-Water Reaction Based on Engineering Approach With Particle Method

Wataru Kosaka, Akihiro Uchibori, Hideki Yanagisawa, Takashi Takata, Sunghyon Jang

Proc. ASME. ICONE28, Volume 2: Nuclear Fuels, Research, and Fuel Cycle; Nuclear Codes and Standards; Thermal-Hydraulics, V002T07A002, August 4–6, 2021

Paper No: ICONE28-61345

DOI: https://doi.org/10.1115/ICONE28-61345

View Paper

Topics: Boilers, Particulate matter, Sodium, Sodium fast reactors, Water

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

View Paper

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

Proceedings Papers

Preliminary Transient Analysis for LBE-Cooled Fast Reactor BLESS-D

Mian Xing, Linsen Li, Gang Zheng, Junlang Wen, Chunyuan Liu, Yeoh Eing Yee, Zhen Luo, Peidong Sun, Jinjun Feng

Paper No: ICONE28-63220

DOI: https://doi.org/10.1115/ICONE28-63220

View Paper

Topics: Fast neutron reactors, Safety, Transient analysis, Transients (Dynamics), Design, Reactor vessels, Accidents, Boilers, Conceptual design, Coolants

Proceedings Papers

Design of a Novel Test Section for the Lead Fast Reactors Development: The CIRCE-THETIS Facility

Pierdomenico Lorusso, Ivan Di Piazza, Daniele Martelli, Andrea Musolesi, Mariano Tarantino

Proc. ASME. ICONE28, Volume 2: Nuclear Fuels, Research, and Fuel Cycle; Nuclear Codes and Standards; Thermal-Hydraulics, V002T07A032, August 4–6, 2021

Paper No: ICONE28-65575

DOI: https://doi.org/10.1115/ICONE28-65575

View Paper

Topics: Boilers, Design, Fast neutron reactors

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

View Paper

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

Proceedings Papers

Assessment and Analysis of Various Mechanisms in the Coalescence and Breakup Models for Upward Bubbly Flow

Shunran Guan, Jinyu Han, Chenru Zhao, Hanliang Bo

Paper No: ICONE28-64436

DOI: https://doi.org/10.1115/ICONE28-64436

View Paper

Topics: Bubbles, Bubbly flow, Computational fluid dynamics, Simulation, Flow (Dynamics), Boilers, Boiling, Collisions (Physics), Fluids, Heat transfer

Proceedings Papers

Study on the Modeling and Simulation of the Horizontal Steam Generator in VVER-1000

Ru Zhang, Junyan Qing, Xiaolong Bi, Guanfu Jiang, Peiwei Sun, Xinyu Wei

Proc. ASME. ICONE28, Volume 4: Student Paper Competition, V004T14A041, August 4–6, 2021

Paper No: ICONE28-64456

DOI: https://doi.org/10.1115/ICONE28-64456

View Paper

Topics: Boilers, Modeling, Simulation

Proceedings Papers

Equal Forced Time Step Approach to PSA for a Dynamic System – A Case of the Holdup Tank

E. E. Taapopi, H. Wang, J. Zhou

Paper No: ICONE28-64081

DOI: https://doi.org/10.1115/ICONE28-64081

View Paper

Topics: Accidents, Boilers, Computers, Dynamic systems, Errors, Failure, Failure mechanisms, Nuclear power stations, Pressure, Probability

Proceedings Papers

Study on Rotor’s Vibration Characteristics of Helium Circulator of HTR

Jiahao Li

Proc. ASME. ICONE2020, Volume 1: Beyond Design Basis; Codes and Standards; Computational Fluid Dynamics (CFD); Decontamination and Decommissioning; Nuclear Fuel and Engineering; Nuclear Plant Engineering, V001T06A011, August 4–5, 2020

Paper No: ICONE2020-16347

DOI: https://doi.org/10.1115/ICONE2020-16347

View Paper

Topics: Helium, Vibration, Rotors, Shells, Finite element methods, Boilers, Degrees of freedom, Design, Heat, Theoretical analysis

Proceedings Papers

Investigating Structural Response of Pressure Reducing Valve of Supercritical Steam Generator System Under Cyclic Moments, Thermal Transient, and Pressure Loadings

Nak-Kyun Cho, Pavitra Bansal, Antony M. Hurst

Paper No: ICONE2020-16426

DOI: https://doi.org/10.1115/ICONE2020-16426

View Paper

Topics: Boilers, Pressure, Transients (Dynamics), Valves, Pipes, Temperature, Collapse, Engineers, Fatigue, Flow (Dynamics)

Proceedings Papers

Comparative Thermal Analyses Between Theoretical Mode and RELAP5 Code Simulation for OTSG of a Small PWR

Baihui Jiang, Zhiwei Zhou, Zhaoyang Xia, Qian Sun

Proc. ASME. ICONE2020, Volume 3: Student Paper Competition; Thermal-Hydraulics; Verification and Validation, V003T12A018, August 4–5, 2020

Paper No: ICONE2020-16281

DOI: https://doi.org/10.1115/ICONE2020-16281

View Paper

Topics: Boilers, Circuits, Computer software, Construction, Design, Fluids, Heat, Heat transfer, Heat transfer coefficients, Light water reactors

Proceedings Papers

Power Rising and Descending Transient for the OTSG of a Small PWR

Baihui Jiang, Zhiwei Zhou, Zhaoyang Xia, Qian Sun

Proc. ASME. ICONE2020, Volume 3: Student Paper Competition; Thermal-Hydraulics; Verification and Validation, V003T12A019, August 4–5, 2020

Paper No: ICONE2020-16294

DOI: https://doi.org/10.1115/ICONE2020-16294

View Paper

Topics: Flow instability, Pressurized water reactors, Transients (Dynamics), Boilers, Flow (Dynamics), Stability, Two-phase flow, Computer software, Fluids, Heat transfer

Proceedings Papers

Study on Breakdown Features and Characteristics of Film at the Corrugated Plate Corner

Bo Wang, Bowen Chen, Bingzheng Ke, Ru Li, Gongqing Wang, Ruifeng Tian, Chuan Lu

Proc. ASME. ICONE2020, Volume 3: Student Paper Competition; Thermal-Hydraulics; Verification and Validation, V003T13A002, August 4–5, 2020

Paper No: ICONE2020-16005

DOI: https://doi.org/10.1115/ICONE2020-16005

View Paper

Topics: Corners (Structural elements), Film thickness, Separation (Technology), Steam, Water, Air flow, Flow (Dynamics), Liquid films, Reynolds number, Boilers

Proceedings Papers

Modeling of Thermal Hydraulic Characteristics for a LBE-Cooled Fast Reactor Helical Coiled Type Steam Generator

Xueyou Ding, Qinglong Wen, Zhiqiang Chen, Shenhui Ruan, Cheng Cheng

Proc. ASME. ICONE2020, Volume 3: Student Paper Competition; Thermal-Hydraulics; Verification and Validation, V003T13A040, August 4–5, 2020

Paper No: ICONE2020-16741

DOI: https://doi.org/10.1115/ICONE2020-16741

View Paper

Topics: Boilers, Fast neutron reactors, Modeling

Proceedings Papers

Optimization Design for the Configuration Parameters of Helical-Coil Steam Generator Volume

Hongyu Fang, Li Wang, Dahuan Zhu, Rong Cai, Xiaowei Jiang, Dan Zhang, Libo Qian, Dan Wu

Proc. ASME. ICONE2020, Volume 3: Student Paper Competition; Thermal-Hydraulics; Verification and Validation, V003T13A054, August 4–5, 2020

Paper No: ICONE2020-16891

DOI: https://doi.org/10.1115/ICONE2020-16891

View Paper

Topics: Boilers, Design, Genetic algorithms, Optimization, Small modular reactors, Safety, Economics , Flow (Dynamics), Nuclear industry, Temperature

2 3 4 5

NARROW

Thermal Hydraulics Analysis of a High-Performance Once-Through Steam Generator With Annular Narrow Slot Tube

A High-Temperature Gas-Cooled Reactor Simulation System and Its Application Based on VPOWER Platform

A Finnish District Heating Reactor: Background and General Overview

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

Numerical Evaluation of Sodium-Water Reaction Based on Engineering Approach With Particle Method

Dynamic Characteristics Analysis of NuScale in Frequency Domain

Preliminary Transient Analysis for LBE-Cooled Fast Reactor BLESS-D

Design of a Novel Test Section for the Lead Fast Reactors Development: The CIRCE-THETIS Facility

Hydrodynamic Analysis of Steam Generator Under LOCA Conditions

Assessment and Analysis of Various Mechanisms in the Coalescence and Breakup Models for Upward Bubbly Flow

Study on the Modeling and Simulation of the Horizontal Steam Generator in VVER-1000

Equal Forced Time Step Approach to PSA for a Dynamic System – A Case of the Holdup Tank

Study on Rotor’s Vibration Characteristics of Helium Circulator of HTR

Investigating Structural Response of Pressure Reducing Valve of Supercritical Steam Generator System Under Cyclic Moments, Thermal Transient, and Pressure Loadings

Comparative Thermal Analyses Between Theoretical Mode and RELAP5 Code Simulation for OTSG of a Small PWR

Power Rising and Descending Transient for the OTSG of a Small PWR

Study on Breakdown Features and Characteristics of Film at the Corrugated Plate Corner

Modeling of Thermal Hydraulic Characteristics for a LBE-Cooled Fast Reactor Helical Coiled Type Steam Generator

Optimization Design for the Configuration Parameters of Helical-Coil Steam Generator Volume

Journals

Conference Proceedings

eBooks

Resources

Opportunities

Journals

Conference Proceedings

eBooks

Resources

Opportunities

This Feature Is Available To Subscribers Only