Search Results | ASME J. of Nuclear Rad Sci.

1-20 of 44

2 3

Sort by

Sort Order Select

Journal Articles

Dimensionless Profiles of Temperature and Steam Mass Fraction in Flows of Steam-Air Mixtures on a Flat Plate

Michio Murase, Tomonori Suzuki, Yoichi Utanohara, Toshiya Takaki

ASME J of Nuclear Rad Sci. January 2023, 9(1): 011401.

Paper No: NERS-22-1006

DOI: https://doi.org/10.1115/1.4054842

Published Online: July 19, 2022

View Article

Topics: Flow (Dynamics), Steam, Temperature, Turbulence, Condensation, Flat plates, Boundary layer turbulence, Computational fluid dynamics, Computation

Journal Articles

Flash-Boiling Characterization During Ingress of Coolant Event for Dust Issue in ITER

Benjamin Blaisot, Emmanuel Porcheron, Olivier Praud, Véronique Roig

ASME J of Nuclear Rad Sci. July 2022, 8(3): 032301.

Paper No: NERS-21-1149

DOI: https://doi.org/10.1115/1.4053828

Published Online: June 1, 2022

View Article

Topics: Boiling, Coolants, Drops, Dust, Ejectors, Flow (Dynamics), Pressure, Sprays, Vacuum, Water

Journal Articles

Thermal-Hydraulic Safety Assessment of Full-Scale ESBWR Nuclear Reactor Design

S. P. Saraswat, D. Ray, G. Mishra, D. Yadav, V. S. Bhadouria, P. Munshi, C. Allison

ASME J of Nuclear Rad Sci. July 2022, 8(3): 031403.

Paper No: NERS-21-1073

DOI: https://doi.org/10.1115/1.4052014

Published Online: May 26, 2022

View Article

Topics: Accidents, Boiling water reactors, Containment, Design, Pressure, Safety, Steam, Water, Heat, Economics

Journal Articles

Prediction Method for Condensation Heat Transfer in the Presence of Noncondensable Gas for Computational Fluid Dynamics Applications

Michio Murase, Yoichi Utanohara, Akio Tomiyama

ASME J of Nuclear Rad Sci. July 2022, 8(3): 031404.

Paper No: NERS-21-1097

DOI: https://doi.org/10.1115/1.4053051

Published Online: May 26, 2022

View Article

Topics: Condensation, Heat transfer, Steam, Temperature, Temperature distribution, Computational fluid dynamics, Mass transfer, Flat plates

Journal Articles

Simulated Environmental Tests for Selected Advanced Technology Fuel Cladding Solutions

Sami Penttilä, Juha-Matti Autio, Jari Lydman, Aki Toivonen, Seppo Peltonen, Johanna Lukin

ASME J of Nuclear Rad Sci. July 2022, 8(3): 031103.

Paper No: NERS-21-1069

DOI: https://doi.org/10.1115/1.4052974

Published Online: March 15, 2022

View Article

Topics: Cladding systems (Building), Coatings, Fracture (Materials), Fuels, High temperature steam, Pressurized water reactors, Steam, Zirconium, Temperature, Weight (Mass)

Journal Articles

Design of Condensation Heat Transfer Experiment to Evaluate Scaling Distortion in Small Modular Reactor Safety Analysis

Palash K. Bhowmik, J. P. Schlegel, V. Kalra, C. Mills, S. Usman

ASME J of Nuclear Rad Sci. July 2021, 7(3): 031406.

Paper No: NERS-20-1021

DOI: https://doi.org/10.1115/1.4050211

Published Online: April 16, 2021

View Article

Topics: Condensation, Cooling, Design, Flow (Dynamics), Heat transfer, Steam, Test facilities, Temperature, Pressure, Water

Journal Articles

Methodology for Calculating Minor Radioactive Releases From VVER 1000 Using TRACE Code

M. Ruscak, G. Mazzini, A. Dambrosio, A. Musa

ASME J of Nuclear Rad Sci. April 2021, 7(2): 021402.

Paper No: NERS-20-1208

DOI: https://doi.org/10.1115/1.4049854

Published Online: February 26, 2021

View Article

Topics: Accidents, Coolants, Flow (Dynamics), Pressure, Safety, Simulation, Water, Nuclear power stations, Feedwater, Design

Journal Articles

Optimization of the PGV-1000MKO Steam Generator Using Computation Fluid Dynamics

Vasilii Volkov, Luka Golibrodo, Alexey Krutikov, Oleg Kudryavtsev, Yurii Nadinskii, Alexander Skibin, Vladimir Sotskov

ASME J of Nuclear Rad Sci. July 2021, 7(3): 031403.

Paper No: NERS-19-1162

DOI: https://doi.org/10.1115/1.4048234

Published Online: February 19, 2021

View Article

Topics: Flow (Dynamics), Nozzles, Steam, Evaporation, Boilers, Optimization

Journal Articles

Nonhyperbolicity of Conservation Equations of RELAP5 Two-Fluid Model in Nuclear Reactor Safety Results (Investigation and Eigenvalue Analysis)

S. P. Saraswat, P. Munshi, C. Allison

ASME J of Nuclear Rad Sci. January 2021, 7(1): 011402.

Paper No: NERS-19-1022

DOI: https://doi.org/10.1115/1.4047161

Published Online: October 2, 2020

View Article

Topics: Accidents, Boiling water reactors, Eigenvalues, Fluids, Porosity, Pressure, Pressurized water reactors, Light water reactors, Water, Stability

Journal Articles

Steam Condensation Heat Transfer During Initial Blow-Down Period of a Severe Nuclear Accident

Mahesh Kumar Yadav, Maneesh Punetha, Abhinav Bhanawat, Sameer Khandekar, Pavan K. Sharma

ASME J of Nuclear Rad Sci. October 2020, 6(4): 041108.

Paper No: NERS-19-1164

DOI: https://doi.org/10.1115/1.4046910

Published Online: September 4, 2020

View Article

Topics: Accidents, Condensation, Heat flux, Heat transfer, Pressure, Steady state, Steam, Temperature, Transients (Dynamics), Containment

Journal Articles

Analysis Methods for High Energy Line Break Jet Flows in Nuclear Power Plants

Marwan Charrouf, Storm Kauffman, Jin-Kyoo Yoon, Sang-Gyu Lee, Taejoon Kim

ASME J of Nuclear Rad Sci. October 2020, 6(4): 041112.

Paper No: NERS-19-1168

DOI: https://doi.org/10.1115/1.4047441

Published Online: September 4, 2020

View Article

Topics: Computational fluid dynamics, Flow (Dynamics), Jets, Nozzles, Nuclear power stations, Pipes, Pressure, Reflection, Resonance, Waves

Journal Articles

Analysis of the Effect of Vessel Failure and Melt Release on Risk of Containment Failure Due to Ex-Vessel Steam Explosion in Nordic Boiling Water Reactor Using ROAAM+ Framework

Sergey Galushin, Dmitry Grishchenko, Pavel Kudinov

ASME J of Nuclear Rad Sci. October 2020, 6(4): 041113.

Paper No: NERS-19-1170

DOI: https://doi.org/10.1115/1.4047552

Published Online: September 4, 2020

View Article

Topics: Boiling water reactors, Containment, Explosions, Failure, Steam, Vessels, Risk, Accidents, Uncertainty

Journal Articles

Numerical Simulation of a Steam Injector for Passive Residual Heat Removal

Thomas Schulenberg, David Heinze

ASME J of Nuclear Rad Sci. July 2020, 6(3): 031105.

Paper No: NERS-19-1058

DOI: https://doi.org/10.1115/1.4045692

Published Online: June 5, 2020

View Article

Topics: Ejectors, Flow (Dynamics), Nozzles, Pressure, Shock (Mechanics), Steam, Condensation, Computer simulation, Water, Two-phase flow

Journal Articles

Oxidation Behavior of Alumina-Forming Austenitic Steels in Superheated Steam at 700 °C

Bingjie Xiao, Nick Tepylo, Xiao Huang, Zhangjian Zhou, Sami Penttilä

ASME J of Nuclear Rad Sci. July 2020, 6(3): 031109.

Paper No: NERS-19-1078

DOI: https://doi.org/10.1115/1.4044530

Published Online: June 5, 2020

View Article

Topics: Alloys, Oxidation, Steam, Steel, Superheating, Weight (Mass), Spallation (Nuclear physics)

Journal Articles

Analyses of Gas Stratification Erosion by a Vertical Jet in Presence of an Obstacle Using the GOTHIC Code

Michele Andreani, Ralf Kapulla, Stephan Kelm, Domenico Paladino, Sidharth Paranjape

ASME J of Nuclear Rad Sci. April 2020, 6(2): 021110.

Paper No: NERS-19-1072

DOI: https://doi.org/10.1115/1.4046296

Published Online: February 24, 2020

View Article

Topics: Elevations (Drawings), Erosion, Flow (Dynamics), Helium, Pipes, Simulation, Steam, Temperature, Turbulence, Vessels

Journal Articles

Enhanced Accident Tolerance of Thoria-Based Nuclear Fuels

B. Szpunar, J. A. Szpunar

ASME J of Nuclear Rad Sci. January 2020, 6(1): 011108.

Paper No: NERS-19-1046

DOI: https://doi.org/10.1115/1.4044751

Published Online: November 8, 2019

View Article

Topics: Accidents, Atoms, Diffusion (Physics), Fuel rods, Fuels, Helium, Nuclear fuels, Oxygen, Temperature, Temperature gradient

Journal Articles

A Study on Onset of Liquid Entrainment in Low Pressure Depressurization System of Advanced Passive Pressurized Water Reactors

Jun Liao, Katsuhiro Ohkawa, William L. Brown, Richard F. Wright

ASME J of Nuclear Rad Sci. October 2019, 5(4): 041701.

Paper No: NERS-18-1088

DOI: https://doi.org/10.1115/1.4042796

Published Online: July 19, 2019

View Article

Topics: Flow (Dynamics), Pipes, Pressure, Pressurized water reactors, Stratified flow, Water, Steam

Journal Articles

Effect of Steam Temperature and Pressure on the Oxidation of Potential Coating Alloy FeCrAl for Supercritical Water-Cooled Reactor Application

Bingjie Xiao, Xiao Huang, Qi Yang, Prakash Patnaik

ASME J of Nuclear Rad Sci. October 2019, 5(4): 041204.

Paper No: NERS-18-1081

DOI: https://doi.org/10.1115/1.4042500

Published Online: July 19, 2019

View Article

Topics: Alloys, Coatings, Oxidation, Pressure, Steam, Superheating, Temperature, Water, Weight (Mass), High temperature

Journal Articles

Experimental Demonstration of Safety During Extended Station Blackout in an Integral Test Loop of a Natural Circulation Boiling Water Reactor

A. K. Nayak, Mukesh Kumar, A. K. Vishnoi, Vikas Jain, D. K. Chandraker

ASME J of Nuclear Rad Sci. October 2019, 5(4): 041205.

Paper No: NERS-18-1093

DOI: https://doi.org/10.1115/1.4043198

Published Online: July 19, 2019

View Article

Topics: Boiling water reactors, Condensers (steam plant), Coolants, Design, Flow (Dynamics), Heat, Pressure, Safety, Temperature, Test facilities

Journal Articles

Experimental Investigations on Carryover in a Gravity Separation-Based Steam Drum

R. K. Bagul, D. S. Pilkhwal, P. K. Vijayan, J. B. Joshi

ASME J of Nuclear Rad Sci. January 2019, 5(1): 011004.

Paper No: NERS-18-1011

DOI: https://doi.org/10.1115/1.4041791

Published Online: January 24, 2019

View Article

Topics: Drops, Flow (Dynamics), Steam, Water, Particulate matter, Separation (Technology), Gravity (Force)

2 3

Journal citation

NARROW

Dimensionless Profiles of Temperature and Steam Mass Fraction in Flows of Steam-Air Mixtures on a Flat Plate

Flash-Boiling Characterization During Ingress of Coolant Event for Dust Issue in ITER

Thermal-Hydraulic Safety Assessment of Full-Scale ESBWR Nuclear Reactor Design

Prediction Method for Condensation Heat Transfer in the Presence of Noncondensable Gas for Computational Fluid Dynamics Applications

Simulated Environmental Tests for Selected Advanced Technology Fuel Cladding Solutions

Design of Condensation Heat Transfer Experiment to Evaluate Scaling Distortion in Small Modular Reactor Safety Analysis

Methodology for Calculating Minor Radioactive Releases From VVER 1000 Using TRACE Code

Optimization of the PGV-1000MKO Steam Generator Using Computation Fluid Dynamics

Nonhyperbolicity of Conservation Equations of RELAP5 Two-Fluid Model in Nuclear Reactor Safety Results (Investigation and Eigenvalue Analysis)

Steam Condensation Heat Transfer During Initial Blow-Down Period of a Severe Nuclear Accident

Analysis Methods for High Energy Line Break Jet Flows in Nuclear Power Plants

Analysis of the Effect of Vessel Failure and Melt Release on Risk of Containment Failure Due to Ex-Vessel Steam Explosion in Nordic Boiling Water Reactor Using ROAAM+ Framework

Numerical Simulation of a Steam Injector for Passive Residual Heat Removal

Oxidation Behavior of Alumina-Forming Austenitic Steels in Superheated Steam at 700 °C

Analyses of Gas Stratification Erosion by a Vertical Jet in Presence of an Obstacle Using the GOTHIC Code

Enhanced Accident Tolerance of Thoria-Based Nuclear Fuels

A Study on Onset of Liquid Entrainment in Low Pressure Depressurization System of Advanced Passive Pressurized Water Reactors

Effect of Steam Temperature and Pressure on the Oxidation of Potential Coating Alloy FeCrAl for Supercritical Water-Cooled Reactor Application

Experimental Demonstration of Safety During Extended Station Blackout in an Integral Test Loop of a Natural Circulation Boiling Water Reactor

Experimental Investigations on Carryover in a Gravity Separation-Based Steam Drum

Journals

Conference Proceedings

eBooks

Resources

Opportunities

Journals

Conference Proceedings

eBooks

Resources

Opportunities

This Feature Is Available To Subscribers Only