Page 1 | Search Results | ASME J. of Nuclear Rad Sci.

1-20 of 45

Sort by

Sort Order Select

Journal Articles

CFD Calculations of Moderator Heat and Fluid Flow of Small Modular Heavy Water Reactor

Tomas Korinek, Radek Skoda, Martin Lovecky, Ondrej Burian

ASME J of Nuclear Rad Sci.

Paper No: NERS-23-1015

https://doi.org/10.1115/1.4063007

Published Online: July 21, 2023

View Article titled, CFD Calculations of Moderator Heat and Fluid Flow of Small Modular Heavy Water Reactor

Topics: Computational fluid dynamics, Fluid dynamics, Heat, Heavy water reactors, Flow (Dynamics), Cooling systems, Vessels, Buoyancy, Coolants, Engineering simulation

Journal Articles

Design Study of Small Modular Reactor Class Super Fast Reactor Core for In-Vessel Retention

Ryotaro Sasaki, Akifumi Yamaji, Kyota Uchimura

ASME J of Nuclear Rad Sci. April 2023, 9(2): 021501.

Paper No: NERS-21-1135

https://doi.org/10.1115/1.4053827

Published Online: June 15, 2022

View Article titled, Design Study of Small Modular Reactor Class Super Fast Reactor Core for In-Vessel Retention

Topics: Design, Vessels, Cycles, Fuels, Temperature, Fast neutron reactors, Small modular reactors

Journal Articles

Experimental Investigation of Melt Coolability Behavior in an Ex-Vessel Core Catcher: The Effect of Flooding Time

Ganesh V, Parimal P. Kulkarni, Arun K. Nayak

ASME J of Nuclear Rad Sci. July 2022, 8(3): 031401.

Paper No: NERS-21-1060

https://doi.org/10.1115/1.4053220

Published Online: May 26, 2022

View Article titled, Experimental Investigation of Melt Coolability Behavior in an Ex-Vessel Core Catcher: The Effect of Flooding Time

Topics: Floods, Temperature, Vessels, Water

Journal Articles

Deposition of ITER Vacuum Vessel Dust Inside the Pressure Suppression System During a Loss of Coolant Accident: Experimental and Numerical Analyses

Miriam Ibba, Alessio Pesetti, Michele Raucci, Flavio Parozzi, Roberta Lazzeri, Donato Aquaro

ASME J of Nuclear Rad Sci. October 2022, 8(4): 042301.

Paper No: NERS-21-1025

https://doi.org/10.1115/1.4050768

Published Online: March 16, 2022

View Article titled, Deposition of ITER Vacuum Vessel Dust Inside the Pressure Suppression System During a Loss of Coolant Accident: Experimental and Numerical Analyses

Topics: Dust, Water, Containers, Vessels, Pipes

Journal Articles

Computational Fluid Dynamic Analysis of the ESFR Reactor Pit Cooling System in Case of Sodium Leakage

Aleksander Grah, Haileyesus Tsige-Tamirat, Joel Guidez, Antoine Gerschenfeld, Konstantin Mikityuk, Janos Bodi, Enrico Girardi

ASME J of Nuclear Rad Sci. January 2022, 8(1): 011314.

Paper No: NERS-20-1204

https://doi.org/10.1115/1.4051292

Published Online: September 20, 2021

View Article titled, Computational Fluid Dynamic Analysis of the ESFR Reactor Pit Cooling System in Case of Sodium Leakage

Topics: Computational fluid dynamics, Concretes, Cooling, Cooling systems, Design, Heat, Heat flux, Leakage, Reactor vessels, Safety

Journal Articles

Modeling of Reactivity Effects and Transient Behavior of Large Sodium Fast Reactor

Alexander Ponomarev, Konstantin Mikityuk

ASME J of Nuclear Rad Sci. January 2022, 8(1): 011313.

Paper No: NERS-20-1186

https://doi.org/10.1115/1.4051514

Published Online: September 13, 2021

View Article titled, Modeling of Reactivity Effects and Transient Behavior of Large Sodium Fast Reactor

Topics: Flow (Dynamics), Fuels, Modeling, Rods, Sodium, Sodium fast reactors, Temperature, Transients (Dynamics), Electrical conductance, Heat

Journal Articles

New Reactor Safety Measures for the European Sodium Fast Reactor—Part I: Conceptual Design

Joel Guidez, Janos Bodi, Konstantin Mikityuk, Enrico Girardi, Bernard Carluec

ASME J of Nuclear Rad Sci. January 2022, 8(1): 011311.

Paper No: NERS-20-1059

https://doi.org/10.1115/1.4051364

Published Online: August 12, 2021

View Article titled, New Reactor Safety Measures for the European Sodium Fast Reactor—Part I: Conceptual Design

Topics: Heat, Safety, Sodium, Vessels, Pumps, Design, Natural convection, Roofs, Leakage, Water

Journal Articles

New Reactor Safety Measures for the European Sodium Fast Reactor—Part II: Preliminary Assessment

Joel Guidez, Janos Bodi, Konstantin Mikityuk, Enrico Girardi, Jeremy Bittan, Aleksander Grah, Haileyesus Tsige-Tamirat, Pablo Romojaro, Francisco Álvarez-Velarde, Bernard Carluec

ASME J of Nuclear Rad Sci. January 2022, 8(1): 011312.

Paper No: NERS-20-1080

https://doi.org/10.1115/1.4051723

Published Online: August 12, 2021

View Article titled, New Reactor Safety Measures for the European Sodium Fast Reactor—Part II: Preliminary Assessment

Topics: Cooling systems, Design, Heat, Heat transfer, Pumps, Safety, Sodium, Sodium fast reactors, Temperature, Vessels

Journal Articles

Preliminary Assessment of Decay Heat Removal Systems in the ESFR-SMART Design: The Role of Natural Air Convection Around Steam Generators Outer Shells in Accidental Conditions

Jeremy Bittan, Clement Bore, Joel Guidez

ASME J of Nuclear Rad Sci. October 2021, 7(4): 041301.

Paper No: NERS-20-1079

https://doi.org/10.1115/1.4048991

Published Online: April 16, 2021

View Article titled, Preliminary Assessment of Decay Heat Removal Systems in the ESFR-SMART Design: The Role of Natural Air Convection Around Steam Generators Outer Shells in Accidental Conditions

Topics: Boilers, Heat, Reactor vessels, Sodium, Temperature, Vessels, Shells, Design, Energy budget (Physics), Pumps

Journal Articles

Passive and Walk-Away Safe Small and Microreactors for Electricity Generation and Production of Process Heat for Industrial Uses

Mohamed S. El-Genk, Timothy M. Schriener, Luis M. Palomino

ASME J of Nuclear Rad Sci. July 2021, 7(3): 031302.

Paper No: NERS-20-1023

https://doi.org/10.1115/1.4047920

Published Online: February 19, 2021

View Article titled, Passive and Walk-Away Safe Small and Microreactors for Electricity Generation and Production of Process Heat for Industrial Uses

Topics: Electric power generation, Fuels, Heat, Neutrons, Safety, Sodium, Vessels, Design, Metals, Steel

Journal Articles

A Comparative Study on Severe Accident Phenomena Related to Melt Progression in Sodium Fast Reactors and Pressurized Water Reactors

Andrea Bachrata, Fréderic Bertrand, Nathalie Marie, Fréderic Serre

ASME J of Nuclear Rad Sci. July 2021, 7(3): 030801.

Paper No: NERS-20-1040

https://doi.org/10.1115/1.4047921

Published Online: November 11, 2020

View Article titled, A Comparative Study on Severe Accident Phenomena Related to Melt Progression in Sodium Fast Reactors and Pressurized Water Reactors

Topics: Accidents, Pressurized water reactors, Sodium fast reactors, Safety, Vessels

Journal Articles

Computational Fluid Dynamics Thermal Analysis of ITER Pressure Suppression Tanks

Lorenzo Basili, Rosa Lo Frano, Marco Olcese, Igor Sekachev, Donato Aquaro

ASME J of Nuclear Rad Sci. January 2021, 7(1): 012301.

Paper No: NERS-19-1156

https://doi.org/10.1115/1.4048007

Published Online: October 5, 2020

View Article titled, Computational Fluid Dynamics Thermal Analysis of ITER Pressure Suppression Tanks

Topics: Accidents, Computational fluid dynamics, Design, Flanges, Insulation, Pressure, Stress, Temperature, Temperature gradient, Thermal analysis

Journal Articles

Study on Melt Coolability and Water Ingression Through Melt Pool in Scaled Down Core Catcher—The Influence of Vessel Angle

Ganesh V., Parimal P. Kulkarni, Arun K. Nayak

ASME J of Nuclear Rad Sci. January 2021, 7(1): 011301.

Paper No: NERS-19-1182

https://doi.org/10.1115/1.4048235

Published Online: October 5, 2020

View Article titled, Study on Melt Coolability and Water Ingression Through Melt Pool in Scaled Down Core Catcher—The Influence of Vessel Angle

Topics: Temperature, Vessels, Water

Journal Articles

Retention of Molten Corium in Calandria Vessel of PHWR With Moderator Drain Pipe

Pradeep Pandey, Parimal P. Kulkarni, Arun Nayak, Sumit V. Prasad

ASME J of Nuclear Rad Sci. January 2021, 7(1): 011702.

Paper No: NERS-19-1131

https://doi.org/10.1115/1.4046257

Published Online: October 1, 2020

View Article titled, Retention of Molten Corium in Calandria Vessel of PHWR With Moderator Drain Pipe

Topics: Pipes, Temperature, Vessels, Heavy water reactors

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

https://doi.org/10.1115/1.4046910

Published Online: September 4, 2020

View Article titled, Steam Condensation Heat Transfer During Initial Blow-Down Period of a Severe Nuclear Accident

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

Journal Articles

Criticality Characteristics and Sensitivity Analysis of Fukushima Debris Beds Containing MCCI Products

María Freiría López, Michael Buck, Jörg Starflinger

ASME J of Nuclear Rad Sci. October 2020, 6(4): 041110.

Paper No: NERS-19-1166

https://doi.org/10.1115/1.4047094

Published Online: September 4, 2020

View Article titled, Criticality Characteristics and Sensitivity Analysis of Fukushima Debris Beds Containing MCCI Products

Topics: Concretes, Water, Fukushima nuclear disaster, Japan, 2011, Vessels, Sensitivity analysis

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

https://doi.org/10.1115/1.4047552

Published Online: September 4, 2020

View Article titled, 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

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

Journal Articles

Postoperation Dose Rate Estimates for the Very-Small, Long-Life, Modular Reactor

Luis M. Palomino, Mohamed S. El-Genk, Timothy M. Schriener

ASME J of Nuclear Rad Sci. July 2020, 6(3): 031302.

Paper No: NERS-19-1045

https://doi.org/10.1115/1.4045297

Published Online: March 9, 2020

View Article titled, Postoperation Dose Rate Estimates for the Very-Small, Long-Life, Modular Reactor

Topics: Cladding systems (Building), Emissions, Fuels, Neutrons, Photons, Steel, Vessels, Storage, Radioactivity, Isotopes

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

https://doi.org/10.1115/1.4046296

Published Online: February 24, 2020

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

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

Journal Articles

In-Vessel Retention of PHWRs: Experiments at Prototypic Temperatures

Sumit V. Prasad, P. P. Kulkarni, D. C. Yadav, P. K. Verma, A. K. Nayak

ASME J of Nuclear Rad Sci. January 2020, 6(1): 011601.

Paper No: NERS-18-1099

https://doi.org/10.1115/1.4043999

Published Online: November 29, 2019

View Article titled, In-Vessel Retention of PHWRs: Experiments at Prototypic Temperatures

Topics: Temperature, Vessels, Heat transfer, Heavy water reactors

Journal citation

NARROW

Manuscript

CFD Calculations of Moderator Heat and Fluid Flow of Small Modular Heavy Water Reactor

Design Study of Small Modular Reactor Class Super Fast Reactor Core for In-Vessel Retention

Experimental Investigation of Melt Coolability Behavior in an Ex-Vessel Core Catcher: The Effect of Flooding Time

Deposition of ITER Vacuum Vessel Dust Inside the Pressure Suppression System During a Loss of Coolant Accident: Experimental and Numerical Analyses

Computational Fluid Dynamic Analysis of the ESFR Reactor Pit Cooling System in Case of Sodium Leakage

Modeling of Reactivity Effects and Transient Behavior of Large Sodium Fast Reactor

New Reactor Safety Measures for the European Sodium Fast Reactor—Part I: Conceptual Design

New Reactor Safety Measures for the European Sodium Fast Reactor—Part II: Preliminary Assessment

Preliminary Assessment of Decay Heat Removal Systems in the ESFR-SMART Design: The Role of Natural Air Convection Around Steam Generators Outer Shells in Accidental Conditions

Passive and Walk-Away Safe Small and Microreactors for Electricity Generation and Production of Process Heat for Industrial Uses

A Comparative Study on Severe Accident Phenomena Related to Melt Progression in Sodium Fast Reactors and Pressurized Water Reactors

Computational Fluid Dynamics Thermal Analysis of ITER Pressure Suppression Tanks

Study on Melt Coolability and Water Ingression Through Melt Pool in Scaled Down Core Catcher—The Influence of Vessel Angle

Retention of Molten Corium in Calandria Vessel of PHWR With Moderator Drain Pipe

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

Criticality Characteristics and Sensitivity Analysis of Fukushima Debris Beds Containing MCCI Products

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

Postoperation Dose Rate Estimates for the Very-Small, Long-Life, Modular Reactor

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

In-Vessel Retention of PHWRs: Experiments at Prototypic Temperatures

Journals

Conference Proceedings

eBooks

Resources

Opportunities

Journals

Conference Proceedings

eBooks

Resources

Opportunities

This Feature Is Available To Subscribers Only