Search Results | ASME J. of Nuclear Rad Sci.

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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.

Paper No: NERS-21-1018

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

Published Online: May 9, 2022

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

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

Necessity of Coordinating Nondestructive Examination Requirement for Nuclear Power Plant

Chongzhi Wu, Haoming Sun, Zhenguo Peng, Benzheng Wang

ASME J of Nuclear Rad Sci.

Paper No: NERS-21-1177

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

Published Online: March 23, 2022

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Topics: Nondestructive evaluation, Nuclear power stations, Design, Inspection, China, Construction, Engineering disciplines, Manufacturing, 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): 031401.

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

Comparative Study on the Impact of ENDF/B-VII.1 Nuclear Library Uncertainty on the CERCER and CERMET Fueled ADS Calculation Results Using Monte Carlo Method Codes

Thanh Mai Vu, Donny Hartanto

ASME J of Nuclear Rad Sci.

Paper No: NERS-21-1143

DOI: https://doi.org/10.1115/1.4054080

Published Online: March 12, 2022

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Topics: Cermets, Monte Carlo methods, Uncertainty, Neutrons, Cross section (Physics), Design, Fuels, Isotopes, Nuclear fuel cycle, Reliability

Journal Articles

Flash-Boiling Characterization During Ingress of Coolant Event (ICE) for Dust Issue in Iter

Benjamin Blaisot, Emmanuel Porcheron, Olivier Praud, ROIG Véronique

ASME J of Nuclear Rad Sci.

Paper No: NERS-21-1149

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

Published Online: February 11, 2022

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Topics: Boiling, Coolants, Dust, Two-phase flow, Vacuum, Erosion, Flow (Dynamics), Hydrogen, Leakage, Plasmas (Ionized gases)

Journal Articles

Steady-State Sub-Channel Thermalhydraulic Assessment of a Full-Scale PWR-SMR Fuel Assembly with Conventional and Advanced Fuels

A. M. Bayomy, Blair Bromley, Armando Nava Dominguez, Sam Kelly

ASME J of Nuclear Rad Sci.

Paper No: NERS-21-1184

DOI: https://doi.org/10.1115/1.4053829

Published Online: February 11, 2022

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Topics: Fuels, Manufacturing, Pressurized water reactors, Steady state, Coatings, Safety, Accidents, Nuclear industry, Performance characterization, Temperature

Journal Articles

Review of Methods and Results for Reactor Physics Analysis of Thorium-Based Fuels From Irradiation Experiments Conducted in NRU

T. Sinh Nguyen, Xiaolin Wang, Blair Bromley

ASME J of Nuclear Rad Sci.

Paper No: NERS-21-1117

DOI: https://doi.org/10.1115/1.4053691

Published Online: January 26, 2022

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Topics: Fuels, Irradiation (Radiation exposure), Physics, Cycles, Uranium, Chalk, Nuclear power, Pressure, Rivers, Safety

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. April 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. April 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. April 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. April 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. April 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. April 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. April 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. April 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

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

Satya Prakash Saraswat, Dipanjan Ray, Gaurav Mishra, Deepak Yadav, Vikesh Singh Bhadouria, Prabhat Munshi, Chris Allison

ASME J of Nuclear Rad Sci.

Paper No: NERS-21-1073

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

Published Online: August 6, 2021

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Topics: Nuclear design, Safety, Design, Accidents, Nuclear reactors, Water, Boiling, Boiling water reactors, Carbon dioxide, Damage

Journal Articles

History of the ESFR SMART Project

Joel Guidez

ASME J of Nuclear Rad Sci. April 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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Manuscript

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

Dr. Romney B. Duffey on His 80th Birthday

Necessity of Coordinating Nondestructive Examination Requirement for Nuclear Power Plant

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

Comparative Study on the Impact of ENDF/B-VII.1 Nuclear Library Uncertainty on the CERCER and CERMET Fueled ADS Calculation Results Using Monte Carlo Method Codes

Flash-Boiling Characterization During Ingress of Coolant Event (ICE) for Dust Issue in Iter

Steady-State Sub-Channel Thermalhydraulic Assessment of a Full-Scale PWR-SMR Fuel Assembly with Conventional and Advanced Fuels

Review of Methods and Results for Reactor Physics Analysis of Thorium-Based Fuels From Irradiation Experiments Conducted in NRU

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

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

History of the ESFR SMART Project

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