Search Results | ASME J. of Nuclear Rad Sci.

1-20 of 80

2 3 4

Sort by

Sort Order Select

Journal Articles

Technical Evaluation Method of Mechanical Equipment Item Substitution in the Procurement and Construction Process of Nuclear Power Plant

Jindong Zhang, Chongzhi Wu

ASME J of Nuclear Rad Sci. January 2023, 9(1): 011801.

Paper No: NERS-22-1014

DOI: https://doi.org/10.1115/1.4054878

Published Online: July 19, 2022

View Article

Topics: Construction, Design, Evaluation methods, Nuclear power stations, Failure mechanisms, Nuclear power

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

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

View Article

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

Journal Articles

High Reliability Microgrid for a Nuclear Facility Emergency Power Supply

Gerard R. Lekhema, Willem A. Cronje, Ian Korir

ASME J of Nuclear Rad Sci. July 2022, 8(3): 031802.

Paper No: NERS-19-1062

DOI: https://doi.org/10.1115/1.4046353

Published Online: May 27, 2022

View Article

Topics: Microgrids, Reliability, Batteries, Diesel generators, Failure, Risk-based design, Emergency power, Probability, Nuclear power stations

Journal Articles

Synergy of a Small Modular Reactor for Addressing Remote Communities Non-Nuclear Waste

Glenn Harvel

ASME J of Nuclear Rad Sci. July 2022, 8(3): 031302.

Paper No: NERS-21-1100

DOI: https://doi.org/10.1115/1.4052808

Published Online: May 26, 2022

View Article

Topics: Fuels, Heat, Nuclear power stations, Plastics, Pyrolysis, Small modular reactors, Heating, Syngas, Temperature, Biochar

Journal Articles

Inverse Heat Conduction Problem in Estimating Nuclear Power Plant Piping Performance

S. A. Cancemi, R. Lo Frano

ASME J of Nuclear Rad Sci. July 2022, 8(3): 034501.

Paper No: NERS-20-1206

DOI: https://doi.org/10.1115/1.4053689

Published Online: May 26, 2022

View Article

Topics: Filters, Pipes, Signals, Stress, Temperature, Monitoring systems, Nuclear power stations

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

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

View Article

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

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

Comparison of the ENDF/B-VII.0, ENDF/B-VII.1, ENDF/B-VIII.0, and JEFF-3.3 Libraries for the Nuclear Design Calculations of the Nuclear Power Plant Krško With the CORD-2 System

Marjan Kromar, Bojan Kurinčič

ASME J of Nuclear Rad Sci. October 2022, 8(4): 041501.

Paper No: NERS-21-1014

DOI: https://doi.org/10.1115/1.4050991

Published Online: March 15, 2022

View Article

Topics: Boron, Cycles, Fuels, Manufacturing, Neutrons, Nuclear design, Nuclear power stations, Nuclear fission, Cross section (Physics), Rods

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

View Article

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

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

Developing and Implementing Artificial Intelligence-Based Classifier for Requirements Engineering

Santeri Myllynen, Ilpo Suominen, Tapani Raunio, Rasmus Karell, Jussi Lahtinen

ASME J of Nuclear Rad Sci. October 2021, 7(4): 041201.

Paper No: NERS-20-1102

DOI: https://doi.org/10.1115/1.4049722

Published Online: April 16, 2021

View Article

Topics: Algorithms, Design, Engineering disciplines, Natural language processing, Safety, Nuclear power stations, Decision making, Nuclear power, Workflow, Artificial intelligence

Journal Articles

Investigating Small Modular Reactor's Design Limits for Its Flexible Operation With Photovoltaic Generation in Microcommunities

Kalpesh Joshi, Bikash Poudel, Ramakrishna (Rama) Gokaraju

ASME J of Nuclear Rad Sci. July 2021, 7(3): 031303.

Paper No: NERS-20-1051

DOI: https://doi.org/10.1115/1.4048896

Published Online: March 16, 2021

View Article

Topics: Design, Nuclear power stations, Simulation, Small modular reactors, Stress, Turbines, Power systems (Machinery), Governors, Steady state, Flow (Dynamics)

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

Prediction of Potential Offsite TEDE, Excess Cancer Risk, Dominant Exposure Pathways, and Activity Concentration for Hypothetical Onsite Soil Contamination at the Proposed Rooppur Nuclear Power Plant

Md. Ashraful Islam, Md. Hossain Sahadath

ASME J of Nuclear Rad Sci. July 2021, 7(3): 034502.

Paper No: NERS-20-1033

DOI: https://doi.org/10.1115/1.4048123

Published Online: February 19, 2021

View Article

Topics: Agricultural pollution, Cancer, Nuclear power stations, Radioisotopes, Risk, Soil, Nuclides

Journal Articles

The Evaluation of the Primary Circuit Passivation Layer Formed After Hot Functional Tests at the EMO3

Pavel Kůs, Martin Kronďák, Martin Skala, Alena Kobzová, Petr Brabec, Patricie Halodová, Janka Mihóková, Štefan Tkáč, Anna Černá

ASME J of Nuclear Rad Sci. April 2021, 7(2): 021804.

Paper No: NERS-20-1149

DOI: https://doi.org/10.1115/1.4049281

Published Online: January 28, 2021

View Article

Topics: Circuits, Nuclear power stations, Hydrogen, Magnetite, Water, Microscopy

Journal Articles

Message From Shoujun Wang, Chinese Nuclear Society President

Shoujun Wang

ASME J of Nuclear Rad Sci. January 2021, 7(1): 010205.

Paper No: NERS-20-1162

DOI: https://doi.org/10.1115/1.4048634

Published Online: December 14, 2020

View Article

Topics: China, Nuclear engineering, Nuclear power, Radiation (Physics), Carbon, Climate change, Construction, Japan Society of Mechanical Engineers, Nuclear industry, Nuclear power stations

2 3 4

Journal citation

NARROW

Manuscript

Technical Evaluation Method of Mechanical Equipment Item Substitution in the Procurement and Construction Process of Nuclear Power Plant

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

Necessity of Coordinating Nondestructive Examination Requirement for Nuclear Power Plant

High Reliability Microgrid for a Nuclear Facility Emergency Power Supply

Synergy of a Small Modular Reactor for Addressing Remote Communities Non-Nuclear Waste

Inverse Heat Conduction Problem in Estimating Nuclear Power Plant Piping Performance

Dr. Romney B. Duffey on His 80th Birthday

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

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

Comparison of the ENDF/B-VII.0, ENDF/B-VII.1, ENDF/B-VIII.0, and JEFF-3.3 Libraries for the Nuclear Design Calculations of the Nuclear Power Plant Krško With the CORD-2 System

Nuclear Regulatory Acceptance of Certified Process Data Reconciliation

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

Developing and Implementing Artificial Intelligence-Based Classifier for Requirements Engineering

Investigating Small Modular Reactor's Design Limits for Its Flexible Operation With Photovoltaic Generation in Microcommunities

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

Prediction of Potential Offsite TEDE, Excess Cancer Risk, Dominant Exposure Pathways, and Activity Concentration for Hypothetical Onsite Soil Contamination at the Proposed Rooppur Nuclear Power Plant

The Evaluation of the Primary Circuit Passivation Layer Formed After Hot Functional Tests at the EMO3

Message From Shoujun Wang, Chinese Nuclear Society President

Journals

Conference Proceedings

eBooks

Resources

Opportunities

Journals

Conference Proceedings

eBooks

Resources

Opportunities

This Feature Is Available To Subscribers Only