Search Results | ICONE | ASME Digital Collection

1-20 of 31

Sort by

Sort Order Select

Proceedings Papers

Development and Verification of Containment Heat Sink Module in Severe Accident Code

Zhi Yang, Peng Zhou, Lin Chen, Yixuan Cheng, Hao Zhang, Yanhua Yang, Yichen Mao

Proc. ASME. ICONE29, Volume 14: Computer Code Verification and Validation; Nuclear Education and Public Acceptance, V014T14A002, August 8–12, 2022

Paper No: ICONE29-91386

DOI: https://doi.org/10.1115/ICONE29-91386

View Paper

Topics: Accidents, Containment, Heat sinks, Heat transfer

Proceedings Papers

Implementation and Comparison of Super Homogenization Method Based on Monte Carlo and Deterministic Codes

Yuan Yuan, Guoming Liu, Xiaodong Huo

Proc. ASME. ICONE29, Volume 14: Computer Code Verification and Validation; Nuclear Education and Public Acceptance, V014T14A006, August 8–12, 2022

Paper No: ICONE29-92520

DOI: https://doi.org/10.1115/ICONE29-92520

View Paper

Topics: Chemical kinetics, Cross section (Physics), Fast neutron reactors, Geometry, Manufacturing, Modeling, Physics, Relaxation (Physics), Very high temperature reactors

Proceedings Papers

Verification and Validation of JMCT Monte Carlo Code in CPR1000

Yaoxin Ye, Jun Zhao, Pengfei Bao

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

View Paper

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 Aerosol Growth and Deposition Properties Affected by Steam Condensation

Zhaoyang Xia, Zhiwei Zhou

Proc. ASME. ICONE29, Volume 14: Computer Code Verification and Validation; Nuclear Education and Public Acceptance, V014T14A001, August 8–12, 2022

Paper No: ICONE29-89271

DOI: https://doi.org/10.1115/ICONE29-89271

View Paper

Topics: Aerosols, Condensation, Steam

Proceedings Papers

Verification and Validation of the Fuel Assembly Bypass Flow Analysis Code PEONY V1.0

Changyi Chen, Jingwen Yan, Yanyan Xi, Yuxiang Zhang, Weicai Li, Change Wu, Qifeng Lv, Shuangye Ran

Proc. ASME. ICONE29, Volume 14: Computer Code Verification and Validation; Nuclear Education and Public Acceptance, V014T14A003, August 8–12, 2022

Paper No: ICONE29-91541

DOI: https://doi.org/10.1115/ICONE29-91541

View Paper

Topics: Flow (Dynamics), Fuels, Manufacturing

Proceedings Papers

Construction of the Failed Fuel Information Database Platform

Xin Liu, Changzheng Li, Yang Wang, Hongyang Zhang, Yongjun Deng

Proc. ASME. ICONE29, Volume 14: Computer Code Verification and Validation; Nuclear Education and Public Acceptance, V014T14A008, August 8–12, 2022

Paper No: ICONE29-93281

DOI: https://doi.org/10.1115/ICONE29-93281

View Paper

Topics: Construction, Databases, Fuels, Manufacturing

Proceedings Papers

Development and Verification of Heat Pipe and Fin Radiation Heat Dissipation Program Based on MOOSE Platform

Sipeng Wang, Xiaoquan Chen, Rui Tian

Proc. ASME. ICONE29, Volume 14: Computer Code Verification and Validation; Nuclear Education and Public Acceptance, V014T14A005, August 8–12, 2022

Paper No: ICONE29-92418

DOI: https://doi.org/10.1115/ICONE29-92418

View Paper

Topics: Energy dissipation, Fins, Heat, Heat pipes, Radiation (Physics)

Proceedings Papers

The Numerical Method Research for Simulating the SMR Steady-State Primary System Flow and Head Loss

Zhongying Ma, Ge Li, Ting Wang, Jinggang Li

Proc. ASME. ICONE29, Volume 14: Computer Code Verification and Validation; Nuclear Education and Public Acceptance, V014T14A007, August 8–12, 2022

Paper No: ICONE29-92987

DOI: https://doi.org/10.1115/ICONE29-92987

View Paper

Topics: Flow (Dynamics), Numerical analysis, Steady state, Pressure, Design, Nuclear reactor coolants, Finite element analysis, Finite element methods, Hydraulics

Proceedings Papers

A Two-Phase Flow Computation Code Based on Two-Fluid Seven-Equation Model

Hao Zhang, Yanhua Yang

Proc. ASME. ICONE29, Volume 14: Computer Code Verification and Validation; Nuclear Education and Public Acceptance, V014T14A004, August 8–12, 2022

Paper No: ICONE29-92367

DOI: https://doi.org/10.1115/ICONE29-92367

View Paper

Topics: Computation, Fluids, Two-phase flow, Equilibrium (Physics), Partial differential equations, Differential equations, Momentum, Pressure, Shock (Mechanics)

Proceedings Papers

CFD Validation With a PIV Provided Experimental Data for the Coolant Velocity Measurement in Reactor Vessel Down-Comer

Abdelgadir Eltayeb, Sichao Tan, Ayodeji A. Ala, Zhang Qi, Nisrene M. Ahmed

Proc. ASME. ICONE26, Volume 4: Nuclear Safety, Security, and Cyber Security; Computer Code Verification and Validation, V004T15A016, July 22–26, 2018

Paper No: ICONE26-82212

DOI: https://doi.org/10.1115/ICONE26-82212

View Paper

Topics: Computational fluid dynamics, Coolants, Reactor vessels, Velocity measurement, Fluid dynamics, Pressurized water reactors, Boundary-value problems, Cylinders, Engineering simulation, Flow (Dynamics)

Proceedings Papers

OECD-NEA Expert Group on Multi-Physics Experimental Data, Benchmarks and Validation

Timothy Valentine, Kostadin Ivanov, Maria Avramova, Alessandro Petruzzi, Jean-Pascal Hudelot, Upendra Rohatgi, Kiril Velkov

Proc. ASME. ICONE26, Volume 4: Nuclear Safety, Security, and Cyber Security; Computer Code Verification and Validation, V004T15A009, July 22–26, 2018

Paper No: ICONE26-81571

DOI: https://doi.org/10.1115/ICONE26-81571

View Paper

Topics: Physics, Linkages, Modeling, Nuclear power, Simulation, Underpinning

Proceedings Papers

Stand-Alone Containment Analysis of the Phébus FPT-3 Test With the ASTEC and the MELCOR Codes

Bruno Gonfiotti, Sandro Paci

Proc. ASME. ICONE26, Volume 4: Nuclear Safety, Security, and Cyber Security; Computer Code Verification and Validation, V004T15A002, July 22–26, 2018

Paper No: ICONE26-81139

DOI: https://doi.org/10.1115/ICONE26-81139

View Paper

Topics: Containment, Accidents, Aerosols, Sensitivity analysis, Computer simulation, Fuels, Pressurized water reactors, Safety, Thermal hydraulics, Transients (Dynamics)

Proceedings Papers

JSNT-S: A Parallel 3D Discrete Ordinates Radiation Transport Code on Structured Mesh

Tangpei Cheng, Zeyao Mo, Chao Yang, Lili Wen, Li Deng

Proc. ASME. ICONE26, Volume 4: Nuclear Safety, Security, and Cyber Security; Computer Code Verification and Validation, V004T15A017, July 22–26, 2018

Paper No: ICONE26-82252

DOI: https://doi.org/10.1115/ICONE26-82252

View Paper

Topics: Radiation (Physics), Algorithms, Computer programming, Computers, Construction

Proceedings Papers

Validation of Film Evaporation Model in GASFLOW-MPI

Li Yabing, Zhang Han, Xiao Jianjun

Proc. ASME. ICONE26, Volume 4: Nuclear Safety, Security, and Cyber Security; Computer Code Verification and Validation, V004T15A003, July 22–26, 2018

Paper No: ICONE26-81249

DOI: https://doi.org/10.1115/ICONE26-81249

View Paper

Topics: Evaporation, Containment, Heat, Wall temperature, Air flow, Computational fluid dynamics, Cooling systems, Heating, Nuclear power stations, Safety

Proceedings Papers

Verification of Shielding Calculation Capability of RMC With H.B.Robinson-2 Pressure Vessel Benchmark

Junjie Rao, Xiaotong Shang, Kan Wang

Proc. ASME. ICONE26, Volume 4: Nuclear Safety, Security, and Cyber Security; Computer Code Verification and Validation, V004T15A010, July 22–26, 2018

Paper No: ICONE26-81694

DOI: https://doi.org/10.1115/ICONE26-81694

View Paper

Topics: Pressure vessels, Computational methods, Neutron flux, Neutrons, Nuclear fission, Cavities, China, Neutron sources, Nuclear fuel cycle, Teams

Proceedings Papers

A Simplified Numerical Benchmark for Pool-Type Sodium Fast Reactors

Stefan Radman, Carlo Fiorina, Konstantin Mikityuk, Andreas Pautz

Proc. ASME. ICONE26, Volume 4: Nuclear Safety, Security, and Cyber Security; Computer Code Verification and Validation, V004T15A018, July 22–26, 2018

Paper No: ICONE26-82260

DOI: https://doi.org/10.1115/ICONE26-82260

View Paper

Topics: Sodium fast reactors, Physics, Modeling, Geometry, Neutrons, Simulation, Testing, Thermal hydraulics

Proceedings Papers

Development of Neutronics and Thermal-Hydraulics Coupled Code for Accelerator Driven Subcritical Systems

Run Luo, Pengfei Wang, Xinyu Wei, Shripad T. Revankar, Fuyu Zhao

Proc. ASME. ICONE26, Volume 4: Nuclear Safety, Security, and Cyber Security; Computer Code Verification and Validation, V004T15A004, July 22–26, 2018

Paper No: ICONE26-81276

DOI: https://doi.org/10.1115/ICONE26-81276

View Paper

Topics: Thermal hydraulics, Steady state, Transients (Dynamics), Computer simulation, Dynamic models, Engineering simulation, Fuels, Neutron sources, Neutrons, Simulation

Proceedings Papers

Numerical Investigation of Corium Coolability in Core Catcher: Sensitivity to Modeling Parameters

Liancheng Guo, Andrei Rineiski

Proc. ASME. ICONE26, Volume 4: Nuclear Safety, Security, and Cyber Security; Computer Code Verification and Validation, V004T15A011, July 22–26, 2018

Paper No: ICONE26-81841

DOI: https://doi.org/10.1115/ICONE26-81841

View Paper

Topics: Modeling, Simulation, Accidents, Vessels, Coolants, Fuels, Sodium, Sodium fast reactors, Fast neutron reactors, Fluid dynamics

Proceedings Papers

Moving From V&V to V&V&C in Nuclear Thermal-Hydraulics

Francesco D’Auria, Marco Lanfredini

Proc. ASME. ICONE26, Volume 4: Nuclear Safety, Security, and Cyber Security; Computer Code Verification and Validation, V004T15A019, July 22–26, 2018

Paper No: ICONE26-82574

DOI: https://doi.org/10.1115/ICONE26-82574

View Paper

Topics: Density, Film boiling, Flow (Dynamics), Heat flux, High pressure (Physics), Nucleate boiling, Pipes, Power density, Pressure, Temperature

Proceedings Papers

QUENCH-06 Experiment Post-Test Calculations and Integrated Uncertainty Analysis With RELAP/SCDAPSIM/MOD3.4 and MOD3.5

C. Allison, B. T. Le, G. Gerova, I. Spasov, M. Perez-Ferragut, J. Hohorst

Proc. ASME. ICONE26, Volume 4: Nuclear Safety, Security, and Cyber Security; Computer Code Verification and Validation, V004T15A012, July 22–26, 2018

Paper No: ICONE26-81912

DOI: https://doi.org/10.1115/ICONE26-81912

View Paper

Topics: Uncertainty analysis, Modeling, Heat losses, Internships, Uncertainty, Computer software, Contact resistance, Convection, Experimental analysis, Fuel rods

NARROW

Development and Verification of Containment Heat Sink Module in Severe Accident Code

Implementation and Comparison of Super Homogenization Method Based on Monte Carlo and Deterministic Codes

Verification and Validation of JMCT Monte Carlo Code in CPR1000

Study on Aerosol Growth and Deposition Properties Affected by Steam Condensation

Verification and Validation of the Fuel Assembly Bypass Flow Analysis Code PEONY V1.0

Construction of the Failed Fuel Information Database Platform

Development and Verification of Heat Pipe and Fin Radiation Heat Dissipation Program Based on MOOSE Platform

The Numerical Method Research for Simulating the SMR Steady-State Primary System Flow and Head Loss

A Two-Phase Flow Computation Code Based on Two-Fluid Seven-Equation Model

CFD Validation With a PIV Provided Experimental Data for the Coolant Velocity Measurement in Reactor Vessel Down-Comer

OECD-NEA Expert Group on Multi-Physics Experimental Data, Benchmarks and Validation

Stand-Alone Containment Analysis of the Phébus FPT-3 Test With the ASTEC and the MELCOR Codes

JSNT-S: A Parallel 3D Discrete Ordinates Radiation Transport Code on Structured Mesh

Validation of Film Evaporation Model in GASFLOW-MPI

Verification of Shielding Calculation Capability of RMC With H.B.Robinson-2 Pressure Vessel Benchmark

A Simplified Numerical Benchmark for Pool-Type Sodium Fast Reactors

Development of Neutronics and Thermal-Hydraulics Coupled Code for Accelerator Driven Subcritical Systems

Numerical Investigation of Corium Coolability in Core Catcher: Sensitivity to Modeling Parameters

Moving From V&V to V&V&C in Nuclear Thermal-Hydraulics

QUENCH-06 Experiment Post-Test Calculations and Integrated Uncertainty Analysis With RELAP/SCDAPSIM/MOD3.4 and MOD3.5

Journals

Conference Proceedings

eBooks

Resources

Opportunities

Journals

Conference Proceedings

eBooks

Resources

Opportunities

This Feature Is Available To Subscribers Only