Volume 3 Issue 4 | ASME J. of Nuclear Rad Sci.

Skip Nav Destination

Volume 3, Issue 4

October 2017

ISSN 2332-8983

EISSN 2332-8975

Research Papers

Assessment of Thermal Fatigue Predictions of Pipes With Spectral Methods

Oriol Costa Garrido, Samir El Shawish, Leon Cizelj

ASME J of Nuclear Rad Sci. October 2017, 3(4): 041001. doi: https://doi.org/10.1115/1.4036736

Abstract

View articletitled, Assessment of Thermal Fatigue Predictions of Pipes With Spectral Methods

Open the PDF for in another window

Topics: Fatigue , Fluids , Pipes , Temperature , Fatigue life , Stress , Fluctuations (Physics)

Saturated Pool Nucleate Boiling on Heat Transfer Surface With Deposited Sea Salts

Shinichiro Uesawa, Yasuo Koizumi, Mitsuhiko Shibata, Hiroyuki Yoshida

ASME J of Nuclear Rad Sci. October 2017, 3(4): 041002. doi: https://doi.org/10.1115/1.4036987

Abstract

View articletitled, Saturated Pool Nucleate Boiling on Heat Transfer Surface With Deposited Sea Salts

Open the PDF for in another window

Topics: Boiling , Heat transfer , Seas , Seawater , Temperature , Water , Heat flux , Fluids , Nucleate boiling , Bubbles

Characterization of Thermal Striping in Liquid Sodium With Optical Fiber Sensors

Matthew Weathered, Jordan Rein, Mark Anderson, Paul Brooks, Bryan Coddington

ASME J of Nuclear Rad Sci. October 2017, 3(4): 041003. doi: https://doi.org/10.1115/1.4037118

Abstract

View articletitled, Characterization of Thermal Striping in Liquid Sodium With Optical Fiber Sensors

Open the PDF for in another window

The Effect of Alkali Metal and Alkaline Earth Metal Impurities on the Iodine-Induced Corrosion of CANDU Fuel Sheathing

Graham A. Ferrier, David Kerr, Joseph Metzler, Evan Veryard, Mohsen Farahani, Paul K. Chan, Mark R. Daymond, Emily C. Corcoran

ASME J of Nuclear Rad Sci. October 2017, 3(4): 041004. doi: https://doi.org/10.1115/1.4037115

Abstract

View articletitled, The Effect of Alkali Metal and Alkaline Earth Metal Impurities on the Iodine-Induced Corrosion of CANDU Fuel Sheathing

Open the PDF for in another window

Topics: Alkali metals , Coatings , Corrosion , Deflection , Fuels , Metal impurities , Metals , Stress , Vapors , Oxygen

Experimental Study on Cavitation of a Liquid Lithium Jet for International Fusion Materials Irradiation Facility

Hiroo Kondo, Takuji Kanemura, Tomohiro Furukawa, Yasushi Hirakawa, Eiichi Wakai, Juan Knaster

ASME J of Nuclear Rad Sci. October 2017, 3(4): 041005. doi: https://doi.org/10.1115/1.4036513

Abstract

View articletitled, Experimental Study on Cavitation of a Liquid Lithium Jet for International Fusion Materials Irradiation Facility

Open the PDF for in another window

Topics: Acoustic intensity , Acoustics , Cavitation , Noise (Sound) , Pressure , Sensors , Waves , Flow (Dynamics) , Pipes , Irradiation (Radiation exposure)

An Finite Element Method Study of the Thermal Conductivity of Polycrystalline UO₂

Enze Jin, Chen Liu, Heming He

ASME J of Nuclear Rad Sci. October 2017, 3(4): 041006. doi: https://doi.org/10.1115/1.4037189

Abstract

View articletitled, An Finite Element Method Study of the Thermal Conductivity of Polycrystalline UO<sub>2</sub>

Open the PDF for in another window

Topics: Grain size , Thermal conductivity , Porosity , Entropy , Finite element methods

Thermal Predictions of the AGR-3/4 Experiment With Post Irradiation Examination Measured Time-Varying Gas Gaps

Grant L. Hawkes, James W. Sterbentz, John T. Maki, Binh T. Pham

ASME J of Nuclear Rad Sci. October 2017, 3(4): 041007. doi: https://doi.org/10.1115/1.4037095

Abstract

View articletitled, Thermal Predictions of the AGR-3/4 Experiment With Post Irradiation Examination Measured Time-Varying Gas Gaps

Open the PDF for in another window

An Online Monitoring Technique for Long-Term Operation Using Guided Waves Propagating in Steel Pipe

Francesco Bertoncini, Mauro Cappelli, Francesco Cordella, Marco Raugi

ASME J of Nuclear Rad Sci. October 2017, 3(4): 041008. doi: https://doi.org/10.1115/1.4037204

Abstract

View articletitled, An Online Monitoring Technique for Long-Term Operation Using Guided Waves Propagating in Steel Pipe

Open the PDF for in another window

Topics: Pipes , Waves , Steel

Ex-Vessel Loss of Coolant Accident Analysis of ITER Divertor Cooling System Using Modified RELAP/SCADAPSIM/Mod 4.0

S. P. Saraswat, P. Munshi, A. Khanna, C. Allison

ASME J of Nuclear Rad Sci. October 2017, 3(4): 041009. doi: https://doi.org/10.1115/1.4037188

Abstract

View articletitled, Ex-Vessel Loss of Coolant Accident Analysis of ITER Divertor Cooling System Using Modified RELAP/SCADAPSIM/Mod 4.0

Open the PDF for in another window

Topics: Accidents , Coolants , Flow (Dynamics) , Vessels , Temperature , Heat , Pressure , Cooling systems , Water , Tungsten

Effects of Supersaturated Silicic Acid Concentration on Deposition Rate Around Geological Disposal System

Tsuyoshi Sasagawa, Taiji Chida, Yuichi Niibori

ASME J of Nuclear Rad Sci. October 2017, 3(4): 041010. doi: https://doi.org/10.1115/1.4037163

Abstract

View articletitled, Effects of Supersaturated Silicic Acid Concentration on Deposition Rate Around Geological Disposal System

Open the PDF for in another window

Topics: Density , Flow (Dynamics) , Minerals , Radioactive wastes , Groundwater , Rocks , Radioisotopes

Research and Development of Validation and Drill System for Full Scope of Severe Accident Management Guideline

Zhifei Yang, Yali Chen, Hu Luo

ASME J of Nuclear Rad Sci. October 2017, 3(4): 041011. doi: https://doi.org/10.1115/1.4036892

Abstract

View articletitled, Research and Development of Validation and Drill System for Full Scope of Severe Accident Management Guideline

Open the PDF for in another window

Topics: Accidents , Drills (Tools) , Accident management , Containment , Graphical user interfaces , Industrial research , Safety

Experimental Demonstration of AHWR Safety During Prolonged Station Black Out

Mukesh Kumar, P. K. Verma, A. K. Nayak, A. Rama Rao

ASME J of Nuclear Rad Sci. October 2017, 3(4): 041012. doi: https://doi.org/10.1115/1.4037031

Abstract

View articletitled, Experimental Demonstration of AHWR Safety During Prolonged Station Black Out

Open the PDF for in another window

Topics: Cooling systems , Design , Heat , Safety , Test facilities , Vessels , Water , Temperature , Fukushima nuclear disaster, Japan, 2011

Loss of Core Cooling Test With One Cooling Line Inactive in Vessel Cooling System of High-Temperature Engineering Test Reactor

Yusuke Fujiwara, Takahiro Nemoto, Daisuke Tochio, Masanori Shinohara, Masato Ono, Shoji Takada

ASME J of Nuclear Rad Sci. October 2017, 3(4): 041013. doi: https://doi.org/10.1115/1.4036985

Abstract

View articletitled, Loss of Core Cooling Test With One Cooling Line Inactive in Vessel Cooling System of High-Temperature Engineering Test Reactor

Open the PDF for in another window

Topics: Cooling , Cooling systems , Temperature , Vessels , Water , Concretes , High temperature , Heat , Helium , Coolants

Computational Fluid Dynamics Simulation of Deflagration-to-Detonation Transition in a Full-Scale Konvoi-Type Pressurized Water Reactor

Josef Hasslberger, Peter Katzy, Lorenz R. Boeck, Thomas Sattelmayer

ASME J of Nuclear Rad Sci. October 2017, 3(4): 041014. doi: https://doi.org/10.1115/1.4037094

Abstract

View articletitled, Computational Fluid Dynamics Simulation of Deflagration-to-Detonation Transition in a Full-Scale Konvoi-Type Pressurized Water Reactor

Open the PDF for in another window

Topics: Computational fluid dynamics , Explosions , Flames , Hydrogen , Ignition , Pressure , Pressurized water reactors , Simulation , Combustion , Containment

The Effect of Intrinsic Instabilities on Effective Flame Speeds in Under-Resolved Simulations of Lean Hydrogen–Air Flames

Peter Katzy, Josef Hasslberger, Lorenz R. Boeck, Thomas Sattelmayer

ASME J of Nuclear Rad Sci. October 2017, 3(4): 041015. doi: https://doi.org/10.1115/1.4036984

Abstract

View articletitled, The Effect of Intrinsic Instabilities on Effective Flame Speeds in Under-Resolved Simulations of Lean Hydrogen–Air Flames

Open the PDF for in another window

Topics: Flames , Hydrogen , Simulation

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

ASME J of Nuclear Rad Sci. October 2017, 3(4): 041016. doi: https://doi.org/10.1115/1.4036737

Abstract

View articletitled, 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

Open the PDF for in another window

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

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

ASME J of Nuclear Rad Sci. October 2017, 3(4): 041017. doi: https://doi.org/10.1115/1.4036983

Abstract

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

Open the PDF for in another window

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

Application of Prompt Self-Powered Neutron Detectors to the Lead-Cooled Fast Reactor Demonstrator ALFRED: Validation of the Monte Carlo Model for Selected SPNDs

Luigi Lepore, Romolo Remetti

ASME J of Nuclear Rad Sci. October 2017, 3(4): 041018. doi: https://doi.org/10.1115/1.4037262

Abstract

View articletitled, Application of Prompt Self-Powered Neutron Detectors to the Lead-Cooled Fast Reactor Demonstrator ALFRED: Validation of the Monte Carlo Model for Selected SPNDs

Open the PDF for in another window

Topics: Fast neutron reactors , Irradiation (Radiation exposure) , Neutron flux , Neutrons , Sensors , Signals , Simulation , Instrumentation

Technical Brief

Regulatory Framework for the Decommissioning of Indonesian Nuclear Facilities

Sri Budi Utami, Susetyo Hario Putero

ASME J of Nuclear Rad Sci. October 2017, 3(4): 044501. doi: https://doi.org/10.1115/1.4037078

Abstract

View articletitled, Regulatory Framework for the Decommissioning of Indonesian Nuclear Facilities

Open the PDF for in another window

Topics: Nuclear decommissioning , Nuclear power stations , Safety , Licensing

Research Papers

Assessment of Thermal Fatigue Predictions of Pipes With Spectral Methods

Saturated Pool Nucleate Boiling on Heat Transfer Surface With Deposited Sea Salts

Characterization of Thermal Striping in Liquid Sodium With Optical Fiber Sensors

The Effect of Alkali Metal and Alkaline Earth Metal Impurities on the Iodine-Induced Corrosion of CANDU Fuel Sheathing

Experimental Study on Cavitation of a Liquid Lithium Jet for International Fusion Materials Irradiation Facility

An Finite Element Method Study of the Thermal Conductivity of Polycrystalline UO₂

Thermal Predictions of the AGR-3/4 Experiment With Post Irradiation Examination Measured Time-Varying Gas Gaps

An Online Monitoring Technique for Long-Term Operation Using Guided Waves Propagating in Steel Pipe

Ex-Vessel Loss of Coolant Accident Analysis of ITER Divertor Cooling System Using Modified RELAP/SCADAPSIM/Mod 4.0

Effects of Supersaturated Silicic Acid Concentration on Deposition Rate Around Geological Disposal System

Research and Development of Validation and Drill System for Full Scope of Severe Accident Management Guideline

Experimental Demonstration of AHWR Safety During Prolonged Station Black Out

Loss of Core Cooling Test With One Cooling Line Inactive in Vessel Cooling System of High-Temperature Engineering Test Reactor

Computational Fluid Dynamics Simulation of Deflagration-to-Detonation Transition in a Full-Scale Konvoi-Type Pressurized Water Reactor

The Effect of Intrinsic Instabilities on Effective Flame Speeds in Under-Resolved Simulations of Lean Hydrogen–Air Flames

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

Application of Prompt Self-Powered Neutron Detectors to the Lead-Cooled Fast Reactor Demonstrator ALFRED: Validation of the Monte Carlo Model for Selected SPNDs

Technical Brief

Regulatory Framework for the Decommissioning of Indonesian Nuclear Facilities

Email alerts

RSS Feeds

ASME Journals

ASME Conference Proceedings

ASME eBooks

Resources

Opportunities

Issues

Research Papers

Technical Brief

Email alerts

RSS Feeds

ASME Journals

ASME Conference Proceedings

ASME eBooks

Resources

Opportunities

This Feature Is Available To Subscribers Only