Search Results | ASME J. of Nuclear Rad Sci.

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Journal Articles

Introducing Passive Nuclear Safety in Water-Cooled Reactors: Numerical Simulation and Validation of Natural Convection Heat Transfer and Transport in Packed Beds of Heated Microspheres

Olugbenga O. Noah, Johan F. Slabber, Josua P. Meyer

ASME J of Nuclear Rad Sci. July 2023, 9(3): 031403.

Paper No: NERS-22-1020

DOI: https://doi.org/10.1115/1.4056239

Published Online: February 8, 2023

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Topics: Fluids, Heat transfer, Particulate matter, Simulation, Temperature, Flow (Dynamics), Design, Fuels, Safety, Natural convection

Journal Articles

Machine Learning Metamodel of a Computationally Intense LOCA Code

Landon A. Conner, Clarence L. Worrell, Jun Liao, James P. Spring, Reza A. Karimi, Jeremy S. Marquardt, Joseph D. Wieder

ASME J of Nuclear Rad Sci. July 2023, 9(3): 031402.

Paper No: NERS-22-1002

DOI: https://doi.org/10.1115/1.4056465

Published Online: February 8, 2023

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Topics: Artificial neural networks, Genetic algorithms, Machine learning, Safety, Pressurized water reactors

Journal Articles

Editorial

Igor L. Pioro

ASME J of Nuclear Rad Sci. January 2023, 9(1): 010201.

Paper No: NERS-22-1120

DOI: https://doi.org/10.1115/1.4056024

Published Online: December 2, 2022

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Topics: China, Nuclear engineering, Nuclear reactors, Radiation (Physics), Safety, Statistics

Journal Articles

ARKADIA—For the Innovation of Advanced Nuclear Reactor Design

Hiroyuki Ohshima, Tai Asayama, Tomohiro Furukawa, Masaaki Tanaka, Akihiro Uchibori, Takashi Takata, Akiyuki Seki, Yasuhiro Enuma

ASME J of Nuclear Rad Sci. April 2023, 9(2): 025001.

Paper No: NERS-21-1157

DOI: https://doi.org/10.1115/1.4054726

Published Online: June 15, 2022

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Topics: Design, Optimization, Safety, Thermal hydraulics, Nuclear design, Nuclear reactors, Computer simulation

Journal Articles

Necessity of Coordinating Nondestructive Examination Requirement for Nuclear Power Plant

Chongzhi Wu, Haoming Sun, Zhenguo Peng, Benzheng Wang

ASME J of Nuclear Rad Sci. January 2023, 9(1): 014701.

Paper No: NERS-21-1177

DOI: https://doi.org/10.1115/1.4054169

Published Online: June 7, 2022

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Topics: Design, Nondestructive evaluation, Nuclear power stations, Safety

Journal Articles

Safety of Radioactive Materials Transportation and Storing Assisted by Internet of Things

M. Zorkany, Hassan F. Morsi

ASME J of Nuclear Rad Sci. July 2022, 8(3): 031901.

Paper No: NERS-20-1010

DOI: https://doi.org/10.1115/1.4048113

Published Online: May 27, 2022

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Topics: Heat, Radioactive substances, Safety, Security, Transportation systems, Internet of things, Embedded systems, Sensors, Vehicles, Radiation (Physics)

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

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

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

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

Journal Articles

Testing the Modified Subchannel tempa-sc Code in Comparison With Experiments and Other Computer Codes

A. M. Baisov, A. N. Churkin, V. I. Deev, V. S. Kharitonov

ASME J of Nuclear Rad Sci. July 2022, 8(3): 031101.

Paper No: NERS-21-1101

DOI: https://doi.org/10.1115/1.4053049

Published Online: March 22, 2022

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Topics: Coolants, Fluids, Fuel rods, Heat transfer, Momentum, Temperature, Water, Wall temperature, Flow (Dynamics), Testing

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

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

Journal Articles

Special Issue: EU ESFR-SMART ProjectWord From the Horizon: 2020 EU ESFR-SMART Project Coordinator

Konstantin Mikityuk

ASME J of Nuclear Rad Sci. January 2022, 8(1): 010305.

Paper No: NERS-21-1121

DOI: https://doi.org/10.1115/1.4052641

Published Online: December 14, 2021

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Topics: Safety, Sodium, Sodium fast reactors, Modeling

Journal Articles

Guest Editorial by Gilles Rodriguez

Gilles Rodriguez

ASME J of Nuclear Rad Sci. January 2022, 8(1): 010303.

Paper No: NERS-21-1137

DOI: https://doi.org/10.1115/1.4052719

Published Online: December 14, 2021

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Topics: Carbon, Collaboration, Economics , Energy consumption, Heat, Hydrogen, Industrial capacity, Innovation, Manufacturing systems, Molten salt reactors

Journal Articles

Experiment and Codes to Support Safety Assessments for Sodium Fast Reactors (KASOLA, SOLTEC and KARIFA)

Wolfgang Hering, Joachim Fuchs, Alexandru Onea, Sara Perez-Martin, Thomas Schaub

ASME J of Nuclear Rad Sci. January 2022, 8(1): 011324.

Paper No: NERS-21-1031

DOI: https://doi.org/10.1115/1.4052642

Published Online: December 7, 2021

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Topics: Flow (Dynamics), Safety, Sodium, Temperature, Test facilities, Liquid metals, Boiling, Computational fluid dynamics, Fluids, Instrumentation

Journal Articles

Optimization of the European Sodium Fast Reactor Secondary Sodium Loop as Part of the ESFR-SMART Project

Joel Guidez, Janos Bodi, Konstantin Mikityuk, Enrico Girardi

ASME J of Nuclear Rad Sci. January 2022, 8(1): 011323.

Paper No: NERS-21-1043

DOI: https://doi.org/10.1115/1.4052589

Published Online: October 29, 2021

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Topics: Circuits, Safety, Sodium, Pumps, Pipes, Boilers, Industrial research, Optimization

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

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

Journal Articles

Nuclear Regulatory Acceptance of Certified Process Data Reconciliation

Andy Jansky, Magnus Langenstein

ASME J of Nuclear Rad Sci. April 2022, 8(2): 022101.

Paper No: NERS-20-1199

DOI: https://doi.org/10.1115/1.4051619

Published Online: October 19, 2021

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Topics: Measurement uncertainty, Nuclear power stations, Uncertainty, Safety, Feedwater, Flow (Dynamics)

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

DOI: https://doi.org/10.1115/1.4051292

Published Online: September 20, 2021

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

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

DOI: https://doi.org/10.1115/1.4051364

Published Online: August 12, 2021

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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

DOI: https://doi.org/10.1115/1.4051723

Published Online: August 12, 2021

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

Journal Articles

History of the ESFR SMART Project

Joel Guidez

ASME J of Nuclear Rad Sci. January 2022, 8(1): 010306.

Paper No: NERS-21-1044

DOI: https://doi.org/10.1115/1.4050298

Published Online: August 3, 2021

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Topics: Safety, Sodium fast reactors, Design

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Journal citation

NARROW

Introducing Passive Nuclear Safety in Water-Cooled Reactors: Numerical Simulation and Validation of Natural Convection Heat Transfer and Transport in Packed Beds of Heated Microspheres

Machine Learning Metamodel of a Computationally Intense LOCA Code

Editorial

ARKADIA—For the Innovation of Advanced Nuclear Reactor Design

Necessity of Coordinating Nondestructive Examination Requirement for Nuclear Power Plant

Safety of Radioactive Materials Transportation and Storing Assisted by Internet of Things

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

Dr. Romney B. Duffey on His 80th Birthday

Testing the Modified Subchannel tempa-sc Code in Comparison With Experiments and Other Computer Codes

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

Special Issue: EU ESFR-SMART ProjectWord From the Horizon: 2020 EU ESFR-SMART Project Coordinator

Guest Editorial by Gilles Rodriguez

Experiment and Codes to Support Safety Assessments for Sodium Fast Reactors (KASOLA, SOLTEC and KARIFA)

Optimization of the European Sodium Fast Reactor Secondary Sodium Loop as Part of the ESFR-SMART Project

ESFR-SMART Core Safety Measures and Their Preliminary Assessment

Nuclear Regulatory Acceptance of Certified Process Data Reconciliation

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

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

History of the ESFR SMART Project

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