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

1-12 of 12

Sort by

Sort Order Select

Journal Articles

Feasibility Study on the Application of Boron Carbide for Long Term Reactivity Control in the LOTUS Small Fast Reactor

Thanh Mai Vu, Thi Hong Bui, Le Quang Linh Tran

Publisher: ASME

ASME J of Nuclear Rad Sci. April 2024, 10(2): 021503.

Paper No: NERS-23-1046

https://doi.org/10.1115/1.4063739

Published Online: January 29, 2024

View Article titled, Feasibility Study on the Application of Boron Carbide for Long Term Reactivity Control in the LOTUS Small Fast Reactor

Topics: Control systems, Design, Fast neutron reactors, Fuels, Neutrons, Rods, Coolants, Boron, Absorption, Safety

Journal Articles

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

M. Ruscak, G. Mazzini, A. Dambrosio, A. Musa

Publisher: ASME

ASME J of Nuclear Rad Sci. April 2021, 7(2): 021402.

Paper No: NERS-20-1208

https://doi.org/10.1115/1.4049854

Published Online: February 26, 2021

View Article titled, Methodology for Calculating Minor Radioactive Releases From VVER 1000 Using TRACE Code

Topics: Accidents, Coolants, Flow (Dynamics), Pressure, Safety, Simulation, Water, Nuclear power stations, Feedwater, Design

Journal Articles

Techno-Economic Study on Implementation of Inventory Control Requirements for a Nuclear-Powered Closed-Cycle Gas Turbine Power Plant

Emmanuel O. Osigwe, Arnold Gad-Briggs, Mafel Obhuo, Pericles Pilidis

Publisher: ASME

ASME J of Nuclear Rad Sci. July 2021, 7(3): 031301.

Paper No: NERS-19-1139

https://doi.org/10.1115/1.4048903

Published Online: February 19, 2021

View Article titled, Techno-Economic Study on Implementation of Inventory Control Requirements for a Nuclear-Powered Closed-Cycle Gas Turbine Power Plant

Topics: Closed-cycle gas turbines, Compressors, Control systems, Cycles, Fluids, Pressure, Storage tanks, Stress, Temperature, Valves

Journal Articles

Confluent Modeling of Heterogeneous Safety and Operational Instrumentation and Control Systems

Mithil Parekh, Yuan Gao, Mariana Jockenhoevel-Barttfeld, Karl Waedt

Publisher: ASME

ASME J of Nuclear Rad Sci. July 2020, 6(3): 031802.

Paper No: NERS-17-1277

https://doi.org/10.1115/1.4046262

Published Online: May 5, 2020

View Article titled, Confluent Modeling of Heterogeneous Safety and Operational Instrumentation and Control Systems

Topics: Computer software, Failure, Instrumentation, Modeling, Nuclear power stations, Safety, Control systems, Hardware, Three-dimensional modeling

Journal Articles

Evaluation of the Steam Generator Clogging Phenomena Kinetics by γ -Ray Counting

Patricia Schindler, Pierre Guy Allinei, Laurent Loubet, Veronique Pointeau

Publisher: ASME

ASME J of Nuclear Rad Sci. April 2019, 5(2): 020912.

Paper No: NERS-18-1056

https://doi.org/10.1115/1.4042851

Published Online: March 15, 2019

View Article titled, Evaluation of the Steam Generator Clogging Phenomena Kinetics by γ -Ray Counting

Topics: Boilers, Modeling, Noise (Sound), Sensors, Fluids, Control systems, Crystals, Signals

Journal Articles

Development and Validation of SAS4A Code and Its Application to Analyses on Severe Flow Blockage Accidents in a Sodium-Cooled Fast Reactor

Yoshitaka Fukano

Publisher: ASME

ASME J of Nuclear Rad Sci. January 2019, 5(1): 011001.

Paper No: NERS-17-1166

https://doi.org/10.1115/1.4040649

Published Online: January 24, 2019

View Article titled, Development and Validation of SAS4A Code and Its Application to Analyses on Severe Flow Blockage Accidents in a Sodium-Cooled Fast Reactor

Topics: Cladding systems (Building), Control systems, Coolants, Flow (Dynamics), Fuels, Sodium fast reactors, Accidents, Safety, Melting, Signals

Journal Articles

Markov/CCMT Dynamic Reliability Analysis of the Main and Startup Feedwater Control System in Nuclear Power Plant

Wentao Li, Danying Gu, Henan Zhang

Publisher: ASME

ASME J of Nuclear Rad Sci. October 2018, 4(4): 041011.

Paper No: NERS-17-1290

https://doi.org/10.1115/1.4040888

Published Online: September 10, 2018

View Article titled, Markov/CCMT Dynamic Reliability Analysis of the Main and Startup Feedwater Control System in Nuclear Power Plant

Topics: Control systems, Event history analysis, Failure, Failure mechanisms, Feedwater, Nuclear power stations, Probability, Reliability

Journal Articles

Analyses of the Control System Strategies and Methodology for Part Power Control of the Simple and Intercooled Recuperated Brayton Helium Gas Turbine Cycles for Generation IV Nuclear Power Plants

A. Gad-Briggs, P. Pilidis, T. Nikolaidis

Publisher: ASME

ASME J of Nuclear Rad Sci. October 2017, 3(4): 041016.

Paper No: NERS-16-1170

https://doi.org/10.1115/1.4036737

Published Online: July 31, 2017

View Article titled, Analyses of the Control System Strategies and Methodology for Part Power Control of the Simple and Intercooled Recuperated Brayton Helium Gas Turbine Cycles for Generation IV Nuclear Power Plants

Topics: Compressors, Control systems, Cycles, Flow (Dynamics), Helium, Nuclear power stations, Pressure, Stress, Temperature, Turbines

Journal Articles

Analyses of the Load Following Capabilities of Brayton Helium Gas Turbine Cycles for Generation IV Nuclear Power Plants

A. Gad-Briggs, P. Pilidis, T. Nikolaidis

Publisher: ASME

ASME J of Nuclear Rad Sci. October 2017, 3(4): 041017.

Paper No: NERS-17-1003

https://doi.org/10.1115/1.4036983

Published Online: July 31, 2017

View Article titled, Analyses of the Load Following Capabilities of Brayton Helium Gas Turbine Cycles for Generation IV Nuclear Power Plants

Topics: Cycles, Helium, Nuclear power stations, Stress, Temperature, Design, Thermal energy, Flow (Dynamics), Pressure control, Compressors

Journal Articles

A Space–Time-Dependent Study of Control Rods Withdrawal in a Large-Size Pressurized Water Reactor

Sanjeev Kumar, K. Obaidurrahman, Om Pal Singh, Prabhat Munshi

Publisher: ASME

ASME J of Nuclear Rad Sci. January 2017, 3(1): 011015.

Paper No: NERS-16-1007

https://doi.org/10.1115/1.4034478

Published Online: December 20, 2016

View Article titled, A Space–Time-Dependent Study of Control Rods Withdrawal in a Large-Size Pressurized Water Reactor

Topics: Heat flux, Nucleate boiling, Pressurized water reactors, Rods, Safety, Scram, Spacetime, Thermal hydraulics, Transients (Dynamics), Temperature profiles

Journal Articles

Neutronic Design Features of a Transportable Fluoride-Salt-Cooled High-Temperature Reactor

Kaichao Sun, Lin-Wen Hu, Charles Forsberg

Publisher: ASME

ASME J of Nuclear Rad Sci. July 2016, 2(3): 031003.

Paper No: NERS-15-1184

https://doi.org/10.1115/1.4032873

Published Online: June 17, 2016

View Article titled, Neutronic Design Features of a Transportable Fluoride-Salt-Cooled High-Temperature Reactor

Topics: Coolants, Design, Fuels, Nuclear fuel cycle, Safety, Rods, Particulate matter, Control systems, High temperature

Journal Articles

Multifragmentation Markov Modeling of a Reactor Trip System

Vyacheslav Kharchenko, Valentina Butenko, Oleg Odarushchenko, Vladimir Sklyar

Publisher: ASME

ASME J of Nuclear Rad Sci. July 2015, 1(3): 031005.

Paper No: NERS-14-1037

https://doi.org/10.1115/1.4029342

Published Online: May 14, 2015

View Article titled, Multifragmentation Markov Modeling of a Reactor Trip System

Topics: Computer software, Design, Failure, Modeling, Stiffness, Control systems, Instrumentation, Maintenance, Numerical analysis

Journal citation

NARROW

Feasibility Study on the Application of Boron Carbide for Long Term Reactivity Control in the LOTUS Small Fast Reactor

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

Techno-Economic Study on Implementation of Inventory Control Requirements for a Nuclear-Powered Closed-Cycle Gas Turbine Power Plant

Confluent Modeling of Heterogeneous Safety and Operational Instrumentation and Control Systems

Evaluation of the Steam Generator Clogging Phenomena Kinetics by γ -Ray Counting

Development and Validation of SAS4A Code and Its Application to Analyses on Severe Flow Blockage Accidents in a Sodium-Cooled Fast Reactor

Markov/CCMT Dynamic Reliability Analysis of the Main and Startup Feedwater Control System in Nuclear Power Plant

Analyses of the Control System Strategies and Methodology for Part Power Control of the Simple and Intercooled Recuperated Brayton Helium Gas Turbine Cycles for Generation IV Nuclear Power Plants

Analyses of the Load Following Capabilities of Brayton Helium Gas Turbine Cycles for Generation IV Nuclear Power Plants

A Space–Time-Dependent Study of Control Rods Withdrawal in a Large-Size Pressurized Water Reactor

Neutronic Design Features of a Transportable Fluoride-Salt-Cooled High-Temperature Reactor

Multifragmentation Markov Modeling of a Reactor Trip System

ASME Journals

ASME Conference Proceedings

ASME eBooks

Resources

Opportunities

ASME Journals

ASME Conference Proceedings

ASME eBooks

Resources

Opportunities

This Feature Is Available To Subscribers Only