Search Results | ASME J. of Nuclear Rad Sci.

1-20 of 103

2 3 4 5

Sort by

Sort Order Select

Journal Articles

Development of a Passive Reactor Shutdown Device to Prevent Core Disruptive Accidents in Fast Reactors: A Study on Device Specifications

Koji Morita, Wei Liu, Tatsumi Arima, Yuji Arita, Isamu Sato, Haruaki Matsuura, Yoshihiro Sekio, Hiroshi Sagara, Masatoshi Kawashima

ASME J of Nuclear Rad Sci. October 2023, 9(4): 041302.

Paper No: NERS-22-1136

DOI: https://doi.org/10.1115/1.4056854

Published Online: March 14, 2023

View Article

Topics: Coolants, Flow (Dynamics), Fuels, Sodium, Temperature, Accidents, Transients (Dynamics), Pins (Engineering)

Journal Articles

Development of a Passive Reactor Shutdown Device to Prevent Core Disruptive Accidents in Fast Reactors: A Preliminary Study

Koji Morita, Wei Liu, Tatsumi Arima, Yuji Arita, Isamu Sato, Haruaki Matsuura, Yoshihiro Sekio, Hiroshi Sagara, Masatoshi Kawashima

ASME J of Nuclear Rad Sci. April 2023, 9(2): 021301.

Paper No: NERS-21-1161

DOI: https://doi.org/10.1115/1.4056834

Published Online: March 2, 2023

View Article

Topics: Accidents, Coolants, Fuels, Temperature, Fast neutron reactors, Flow (Dynamics), Pins (Engineering), Transients (Dynamics)

Journal Articles

Assessment of Filtered Containment Venting Strategies for Mitigating Severe Accident Consequences at a Generic Single-Unit CANDU

M. D. Shah, A. C. Morreale, L. S. Lebel

ASME J of Nuclear Rad Sci. January 2023, 9(1): 011701.

Paper No: NERS-22-1025

DOI: https://doi.org/10.1115/1.4055258

Published Online: September 2, 2022

View Article

Topics: Accidents, Containment, Failure, Pressure, Water

Journal Articles

Preliminary Analysis of Reactivity Feedbacks for Inner-Side Chromium Coating

Rofida Hamad Khlifa, Nicolay N. Nikitenkov

ASME J of Nuclear Rad Sci. January 2023, 9(1): 012003.

Paper No: NERS-22-1044

DOI: https://doi.org/10.1115/1.4055012

Published Online: September 1, 2022

View Article

Topics: Boron, Coatings, Fuels, Temperature, Cladding systems (Building), Neutrons, Accidents

Journal Articles

Pearson Correlation and Chi-Squared Methods Applied to the Sensitivity and Uncertainty Analysis of Hydrogen Generation During a BWR STSBO Using MAAP5 and AZTUSIA

Javier Ortiz-Villafuerte, Heriberto Sanchez-Mora, Cesar Queral, Melisa Reyes-Fuentes, Edmundo del-Valle-Gallegos

ASME J of Nuclear Rad Sci.

Paper No: NERS-22-1021

DOI: https://doi.org/10.1115/1.4055011

Published Online: July 15, 2022

View Article

Topics: Boiling water reactors, Hydrogen, Uncertainty analysis, Accidents, Simulation, Explosions, Cladding systems (Building), Failure, Fukushima nuclear disaster, Japan, 2011, Nuclear power stations

Journal Articles

Coupling of ASTEC V2.1 and RASCAL 4.3 Codes to Evaluate the Source Term and the Radiological Consequences of a Loss-of-Cooling Accident at a Spent Fuel Pool

Antonio Guglielmelli, Stefano Ederli, Fulvio Mascari, Federico Rocchi, Pietro Maccari

ASME J of Nuclear Rad Sci. October 2022, 8(4): 041602.

Paper No: NERS-21-1018

DOI: https://doi.org/10.1115/1.4054514

Published Online: June 24, 2022

View Article

Topics: Accidents, Cooling, Emissions, Fukushima nuclear disaster, Japan, 2011, Meteorology, Nuclear power stations, Simulation, Spent nuclear fuels, Wind, Wind velocity

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

Uncertainty Quantification in Support of Severe Accident Analysis Code User Confidence Using MELCOR-DAKOTA

Emmanuel K. Boafo, Emmanuel Numapau Gyamfi

ASME J of Nuclear Rad Sci. July 2022, 8(3): 031703.

Paper No: NERS-21-1094

DOI: https://doi.org/10.1115/1.4053050

Published Online: May 26, 2022

View Article

Topics: Accidents, Hydrogen, Sensitivity analysis, Uncertainty, Uncertainty quantification, Uncertainty analysis, Design, Optimization

Journal Articles

Dr. Romney B. Duffey on His 80th Birthday

Igor Pioro, Richard R. Schultz, Dr. Hideki Kamide, Dr. Sama Bilbao y Leon, Dr. Nils Diaz, Alexander V. Bychkov, Dr. Leon Cizelj, Francesco D'Auria, Dr. Yanping Huang, Dr. Yasuo Koizumi, Tomio Okawa, Dr. Robert Walker, Dr. Robert Youngblood, Enrico Zio

ASME J of Nuclear Rad Sci. July 2022, 8(3): 030201.

Paper No: NERS-22-1030

DOI: https://doi.org/10.1115/1.4054329

Published Online: May 3, 2022

View Article

Topics: Accidents, Design, Electricity (Physics), Governments, Innovation, Japan Society of Mechanical Engineers, Nuclear engineering, Nuclear power, Risk, Safety

Journal Articles

Analysis of the HI-TRAC VW Transfer Cask Dose Rates for Spent Fuel Assemblies Loaded in Nuclear Power Plant Krsko Storage Campaign One

Davor Grgić, Mario Matijević, Paulina Dučkić, Radomir Ječmenica

ASME J of Nuclear Rad Sci. October 2022, 8(4): 041902.

Paper No: NERS-21-1029

DOI: https://doi.org/10.1115/1.4051447

Published Online: March 16, 2022

View Article

Topics: Accidents, Fuels, Hardware, Neutrons, Nuclear power stations, Particulate matter, Spent nuclear fuels, Storage, Uncertainty, Manufacturing

Journal Articles

Utilization of Nuklearna Elektrarna Krško Full Scope Simulator for Plant Operation Optimization, Nuclear Education and Engineering in 20 Years

Matjaž Žvar, Tomaž Žagar

ASME J of Nuclear Rad Sci. October 2022, 8(4): 041701.

Paper No: NERS-21-1022

DOI: https://doi.org/10.1115/1.4052013

Published Online: March 16, 2022

View Article

Topics: Accidents, Design, Drills (Tools), Education, Emergency preparedness, Nuclear power stations, Safety, Optimization, Computers, Spent nuclear fuels

Journal Articles

Experimental Investigation on the Retention of Soluble Particles by Pool Scrubbing

R. Vennemann, M. Klauck, H.-J. Allelein

ASME J of Nuclear Rad Sci. October 2022, 8(4): 044502.

Paper No: NERS-20-1212

DOI: https://doi.org/10.1115/1.4051250

Published Online: March 15, 2022

View Article

Topics: Aerosols, Particulate matter, Water, Accidents, Bubbles

Journal Articles

ESFR-SMART Core Safety Measures and Their Preliminary Assessment

Andrei Rineiski, Clément Mériot, Marco Marchetti, Jiri Krepel, Christine Coquelet-Pascal, Haileyesus Tsige-Tamirat, Francisco Álvarez-Velarde, Enrico Girardi, Konstantin Mikityuk

ASME J of Nuclear Rad Sci. January 2022, 8(1): 011322.

Paper No: NERS-20-1130

DOI: https://doi.org/10.1115/1.4052588

Published Online: October 29, 2021

View Article

Topics: Fuels, Safety, Sodium, Sodium fast reactors, Design, Accidents

Journal Articles

Post-Test Analyses of the CMMR-4 Test

Takuya Yamashita, Hiroshi Madokoro, Ikken Sato

ASME J of Nuclear Rad Sci. April 2022, 8(2): 021701.

Paper No: NERS-21-1055

DOI: https://doi.org/10.1115/1.4051443

Published Online: October 19, 2021

View Article

Topics: Blades, Boiling water reactors, Cutting, Fuels, Heating, Melting, Water, Temperature, Accidents, Permeability

Journal Articles

Optimization of the Nodalization of Nuclear System Thermal-Hydraulic Code Applied on Primary Loop Benchmark

Hong Xu, Aurelian Florin Badea, Xu Cheng

ASME J of Nuclear Rad Sci. April 2022, 8(2): 021404.

Paper No: NERS-21-1036

DOI: https://doi.org/10.1115/1.4050770

Published Online: October 19, 2021

View Article

Topics: Accidents, Coolants, Steady state, Transients (Dynamics), Errors, Flow (Dynamics), Thermal hydraulics, Leakage, Simulation

Journal Articles

Severe Accidents in Sodium-Cooled Fast Reactors: Computational Fluid Dynamics Sensitivity Studies on the Thermal Ablation of Core Catcher

Olivier Czarny, Adrien Collin De L'Hortet, Nicolas Goreaud

ASME J of Nuclear Rad Sci. January 2022, 8(1): 011318.

Paper No: NERS-20-1200

DOI: https://doi.org/10.1115/1.4052306

Published Online: October 4, 2021

View Article

Topics: Ablation (Vaporization technology), Accidents, Temperature, Design, Sodium fast reactors, Computational fluid dynamics

Journal Articles

Safety Method for the Preconceptual Phase of Sodium-Cooled Fast Reactors

S. Ehster, L. Ammirabile, E. Bubelis, B. Carluec, J. B. Droin, E. Girardi

ASME J of Nuclear Rad Sci. January 2022, 8(1): 011304.

Paper No: NERS-20-1078

DOI: https://doi.org/10.1115/1.4050766

Published Online: August 3, 2021

View Article

Topics: Failure, Safety, Heat, Sodium fast reactors, Design, Defense industry, Performance, Accidents

Journal Articles

Systematic Approach to Transboundary Radioactivity Monitoring for Accidents in External Nuclear Power Plants

Kampanart Silva, Piyawan Krisanangkura, Krirerk Phungsara, Chatchai Chaiyasaen, Suchin Udomsomporn

ASME J of Nuclear Rad Sci. October 2021, 7(4): 041701.

Paper No: NERS-20-1099

DOI: https://doi.org/10.1115/1.4049279

Published Online: April 16, 2021

View Article

Topics: Accidents, Meteorology, Nuclear power stations, Plumes (Fluid dynamics), Radiation measurement, Wind, Feedback

Journal Articles

Numerical Simulation of Container Breach and Airborne Release of Solids Due to Mechanical Insults

David L. Y. Louie, San Le, Lindsay N. Gilkey

ASME J of Nuclear Rad Sci. July 2021, 7(3): 031901.

Paper No: NERS-19-1171

DOI: https://doi.org/10.1115/1.4050212

Published Online: April 16, 2021

View Article

Topics: Containers, Damage, Microscale devices, Simulation, Solids, Forklifts, Accidents, Fracture (Materials)

Journal Articles

Simulation of the Super Critical Water Loop Using ATHLET Code During an Abnormal Scenario

Guido Mazzini, Alis Musa, Rostilav Fukac

ASME J of Nuclear Rad Sci. April 2021, 7(2): 021404.

Paper No: NERS-20-1157

DOI: https://doi.org/10.1115/1.4050207

Published Online: March 10, 2021

View Article

Topics: Flow (Dynamics), Pressure, Safety, Simulation, Temperature, Transients (Dynamics), Water, Heat transfer, Pumps, Light water reactors

2 3 4 5

Journal citation

NARROW

Manuscript

Development of a Passive Reactor Shutdown Device to Prevent Core Disruptive Accidents in Fast Reactors: A Study on Device Specifications

Development of a Passive Reactor Shutdown Device to Prevent Core Disruptive Accidents in Fast Reactors: A Preliminary Study

Assessment of Filtered Containment Venting Strategies for Mitigating Severe Accident Consequences at a Generic Single-Unit CANDU

Preliminary Analysis of Reactivity Feedbacks for Inner-Side Chromium Coating

Pearson Correlation and Chi-Squared Methods Applied to the Sensitivity and Uncertainty Analysis of Hydrogen Generation During a BWR STSBO Using MAAP5 and AZTUSIA

Coupling of ASTEC V2.1 and RASCAL 4.3 Codes to Evaluate the Source Term and the Radiological Consequences of a Loss-of-Cooling Accident at a Spent Fuel Pool

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

Uncertainty Quantification in Support of Severe Accident Analysis Code User Confidence Using MELCOR-DAKOTA

Dr. Romney B. Duffey on His 80th Birthday

Analysis of the HI-TRAC VW Transfer Cask Dose Rates for Spent Fuel Assemblies Loaded in Nuclear Power Plant Krsko Storage Campaign One

Utilization of Nuklearna Elektrarna Krško Full Scope Simulator for Plant Operation Optimization, Nuclear Education and Engineering in 20 Years

Experimental Investigation on the Retention of Soluble Particles by Pool Scrubbing

ESFR-SMART Core Safety Measures and Their Preliminary Assessment

Post-Test Analyses of the CMMR-4 Test

Optimization of the Nodalization of Nuclear System Thermal-Hydraulic Code Applied on Primary Loop Benchmark

Severe Accidents in Sodium-Cooled Fast Reactors: Computational Fluid Dynamics Sensitivity Studies on the Thermal Ablation of Core Catcher

Safety Method for the Preconceptual Phase of Sodium-Cooled Fast Reactors

Systematic Approach to Transboundary Radioactivity Monitoring for Accidents in External Nuclear Power Plants

Numerical Simulation of Container Breach and Airborne Release of Solids Due to Mechanical Insults

Simulation of the Super Critical Water Loop Using ATHLET Code During an Abnormal Scenario

Journals

Conference Proceedings

eBooks

Resources

Opportunities

Journals

Conference Proceedings

eBooks

Resources

Opportunities

This Feature Is Available To Subscribers Only