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

1-15 of 15

Sort by

Sort Order Select

Journal Articles

Pyrolysis and High Performance Plasma Treatment Applied to Spent Ion Exchange Resins

Hernán Ariel Castro, Raúl Ariel Rodríguez, Vittorio Luca, Hugo Luis Bianchi

Publisher: ASME

ASME J of Nuclear Rad Sci. April 2019, 5(2): 020901.

Paper No: NERS-18-1045

https://doi.org/10.1115/1.4042193

Published Online: March 15, 2019

View Article titled, Pyrolysis and High Performance Plasma Treatment Applied to Spent Ion Exchange Resins

Topics: Plasmas (Ionized gases), Pyrolysis, Resins, Ion exchange, Temperature

Journal Articles

Glasses for Nuclear Waste Immobilization. Effect of Lutetium Addition on Yttrium Aluminosilicate Glass Crystallization Kinetics

D. C. Lago, M. B. Bortot, M. O. Prado

Publisher: ASME

ASME J of Nuclear Rad Sci. April 2019, 5(2): 020907.

Paper No: NERS-18-1046

https://doi.org/10.1115/1.4042497

Published Online: March 15, 2019

View Article titled, Glasses for Nuclear Waste Immobilization. Effect of Lutetium Addition on Yttrium Aluminosilicate Glass Crystallization Kinetics

Topics: Glass, Yttrium, Crystallization

Journal Articles

Validation of Selected Cesar Friction Models of the ASTECV21 Code Based on Moby Dick Experiments

I. Gómez-García-Toraño, L. Laborde

Publisher: ASME

ASME J of Nuclear Rad Sci. April 2019, 5(2): 020908.

Paper No: NERS-18-1070

https://doi.org/10.1115/1.4042119

Published Online: March 15, 2019

View Article titled, Validation of Selected Cesar Friction Models of the ASTECV21 Code Based on Moby Dick Experiments

Topics: Flow (Dynamics), Friction, Momentum, Pressure, Pressure drop

Journal Articles

Thermal–Hydraulic Design in the Transition Laminar–to–Turbulent Flow Regime

J. Lupiano Contreras, A. S. Doval, P. A. Alberto

Publisher: ASME

ASME J of Nuclear Rad Sci. April 2019, 5(2): 020902.

Paper No: NERS-18-1063

https://doi.org/10.1115/1.4042363

Published Online: March 15, 2019

View Article titled, Thermal–Hydraulic Design in the Transition Laminar–to–Turbulent Flow Regime

Topics: Design, Flow (Dynamics), Uncertainty, Cooling, Heat transfer coefficients

Journal Articles

Preparation of UF 4 by Carbochlorination of U 3 O 8 and Solid-State Halogen Exchange Reaction

Cristina N. Guibaldo, Georgina De Micco, Ana E. Bohé

Publisher: ASME

ASME J of Nuclear Rad Sci. April 2019, 5(2): 020910.

Paper No: NERS-18-1066

https://doi.org/10.1115/1.4042362

Published Online: March 15, 2019

View Article titled, Preparation of UF 4 by Carbochlorination of U 3 O 8 and Solid-State Halogen Exchange Reaction

Topics: Uranium, Carbon, Quartz, X-ray diffraction

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

Nuclear Communication Campaign in Spain: Basic Nuclear Fusion Course

Kevin Fernández-Cosials, Alfonso Barbas, José García Laruelo

Publisher: ASME

ASME J of Nuclear Rad Sci. April 2019, 5(2): 020906.

Paper No: NERS-18-1040

https://doi.org/10.1115/1.4042192

Published Online: March 15, 2019

View Article titled, Nuclear Communication Campaign in Spain: Basic Nuclear Fusion Course

Topics: Nuclear fusion, Nuclear power

Journal Articles

Electrical Power System Modeling of Atucha II Nuclear Power Plant Using etap

Nicolás Alejandro Malinovsky

Publisher: ASME

ASME J of Nuclear Rad Sci. April 2019, 5(2): 020915.

Paper No: NERS-18-1064

https://doi.org/10.1115/1.4042361

Published Online: March 15, 2019

View Article titled, Electrical Power System Modeling of Atucha II Nuclear Power Plant Using etap

Topics: Circuits, Electricity (Physics), Nuclear power stations, Stress, Power systems (Machinery), Modeling, Computer software, Flow (Dynamics), Electronic systems

Journal Articles

Sensitivity Analysis of the Thermal Diffusion Coefficient Effect on the Departure From Nucleate Boiling Ratio With the VIPRE Code

Rosario Delgado-Tardáguila, Marisol Corisco, Antonio Espejo, Daniel Navarro, Javier Riverola

Publisher: ASME

ASME J of Nuclear Rad Sci. April 2019, 5(2): 020909.

Paper No: NERS-18-1057

https://doi.org/10.1115/1.4042358

Published Online: March 15, 2019

View Article titled, Sensitivity Analysis of the Thermal Diffusion Coefficient Effect on the Departure From Nucleate Boiling Ratio With the VIPRE Code

Topics: Design, Fuels, Nucleate boiling, Thermal diffusion, Turbulence, Enthalpy, Momentum, Heat flux, Flow (Dynamics), Sensitivity analysis

Journal Articles

Technical Communication During Nuclear and Radiological Emergencies With the Tools to Support International Assessment and Prognosis

Margarita Tzivaki, Edward J. Waller

Publisher: ASME

ASME J of Nuclear Rad Sci. April 2019, 5(2): 020913.

Paper No: NERS-18-1068

https://doi.org/10.1115/1.4042906

Published Online: March 15, 2019

View Article titled, Technical Communication During Nuclear and Radiological Emergencies With the Tools to Support International Assessment and Prognosis

Topics: Emergencies, Emergency response

Journal Articles

Use of Irradiated Fracture Toughness Values in Nuclear Vessel and Component Design Specifications for Fitness-For-Service Analysis Using the Unified Curve Method

Waleed Ishaque

Publisher: ASME

ASME J of Nuclear Rad Sci. April 2019, 5(2): 020911.

Paper No: NERS-18-1062

https://doi.org/10.1115/1.4042498

Published Online: March 15, 2019

View Article titled, Use of Irradiated Fracture Toughness Values in Nuclear Vessel and Component Design Specifications for Fitness-For-Service Analysis Using the Unified Curve Method

Topics: American Petroleum Institute, Fracture (Materials), Fracture toughness, Junctions, Nozzles, Stress, Vessels, Design, Fitness-for-service, Steel

Journal Articles

Simulation of Nuclear Fuel Behavior in Accident Conditions With the DIONISIO Code

Martín Lemes, Alicia Denis, Alejandro Soba

Publisher: ASME

ASME J of Nuclear Rad Sci. April 2019, 5(2): 020903.

Paper No: NERS-18-1078

https://doi.org/10.1115/1.4042705

Published Online: March 15, 2019

View Article titled, Simulation of Nuclear Fuel Behavior in Accident Conditions With the DIONISIO Code

Topics: Accidents, Cladding systems (Building), Coolants, Fuel rods, Fuels, High temperature, Hydrogen, Simulation, Temperature, Water

Journal Articles

Preliminary Investigations of the Feasibility of In-Vessel Melt Retention Strategies for a Small Modular Reactor Concept

Lena Andriolo, Clément Meriot, Nikolai Bakouta

Publisher: ASME

ASME J of Nuclear Rad Sci. April 2019, 5(2): 020905.

Paper No: NERS-18-1060

https://doi.org/10.1115/1.4042360

Published Online: March 15, 2019

View Article titled, Preliminary Investigations of the Feasibility of In-Vessel Melt Retention Strategies for a Small Modular Reactor Concept

Topics: Vessels

Journal Articles

Micro-Calorimetric Study on the Thermal Stability of N, N-Dimethylhydroxylamine in the APOR Process

Cao Zhi, Yan Taihong, Bian Xiaoyan, Li Chuanbo, Zuo Chen, Zheng Weifang

Publisher: ASME

ASME J of Nuclear Rad Sci. April 2019, 5(2): 020914.

Paper No: NERS-18-1067

https://doi.org/10.1115/1.4042499

Published Online: March 15, 2019

View Article titled, Micro-Calorimetric Study on the Thermal Stability of N, N-Dimethylhydroxylamine in the APOR Process

Topics: Enthalpy, Heat, Temperature, Thermal stability, Metals

Journal Articles

Implementation of Hydrogen Solid Solubility Data and Precipitation Threshold Stresses in the Fuel Rod Code TESPA-ROD

Felix Boldt

Publisher: ASME

ASME J of Nuclear Rad Sci. April 2019, 5(2): 020904.

Paper No: NERS-18-1065

https://doi.org/10.1115/1.4042118

Published Online: March 15, 2019

View Article titled, Implementation of Hydrogen Solid Solubility Data and Precipitation Threshold Stresses in the Fuel Rod Code TESPA-ROD

Topics: Cladding systems (Building), Fuel rods, Heat, Hydrogen, Precipitation, Storage, Stress, Temperature, Transients (Dynamics), Simulation

Journal citation

NARROW

Pyrolysis and High Performance Plasma Treatment Applied to Spent Ion Exchange Resins

Glasses for Nuclear Waste Immobilization. Effect of Lutetium Addition on Yttrium Aluminosilicate Glass Crystallization Kinetics

Validation of Selected Cesar Friction Models of the ASTECV21 Code Based on Moby Dick Experiments

Thermal–Hydraulic Design in the Transition Laminar–to–Turbulent Flow Regime

Preparation of UF 4 by Carbochlorination of U 3 O 8 and Solid-State Halogen Exchange Reaction

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

Nuclear Communication Campaign in Spain: Basic Nuclear Fusion Course

Electrical Power System Modeling of Atucha II Nuclear Power Plant Using etap

Sensitivity Analysis of the Thermal Diffusion Coefficient Effect on the Departure From Nucleate Boiling Ratio With the VIPRE Code

Technical Communication During Nuclear and Radiological Emergencies With the Tools to Support International Assessment and Prognosis

Use of Irradiated Fracture Toughness Values in Nuclear Vessel and Component Design Specifications for Fitness-For-Service Analysis Using the Unified Curve Method

Simulation of Nuclear Fuel Behavior in Accident Conditions With the DIONISIO Code

Preliminary Investigations of the Feasibility of In-Vessel Melt Retention Strategies for a Small Modular Reactor Concept

Micro-Calorimetric Study on the Thermal Stability of N, N-Dimethylhydroxylamine in the APOR Process

Implementation of Hydrogen Solid Solubility Data and Precipitation Threshold Stresses in the Fuel Rod Code TESPA-ROD

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