Volume 6 Issue 4 | ASME J. of Nuclear Rad Sci.

Guest Editorial

Special Section: Selected Papers from ICONE-27

Jovica Riznic, Tomio Okawa, Asif Arastu, Leon Cizelj, Shripad Revankar, Richard Schultz

ASME J of Nuclear Rad Sci. October 2020, 6(4): 040301. doi: https://doi.org/10.1115/1.4047731

View articletitled, Special Section: Selected Papers from ICONE-27

Topics: Japan Society of Mechanical Engineers , Mechanical engineers , Nuclear engineering , Radiation (Physics) , Students , Nuclear power , Engineers , Governments , Industrial research , Maintenance

Special Papers

Analysis on Critical Factors of Marine Organism Impacts on Water Intake Safety at Nuclear Power Plants

Xiaocheng Fu, Fenglei Du, Xiang Pu, Xuan Wang, Fengze Han

ASME J of Nuclear Rad Sci. October 2020, 6(4): 041101. doi: https://doi.org/10.1115/1.4048112

Abstract

View articletitled, Analysis on Critical Factors of Marine Organism Impacts on Water Intake Safety at Nuclear Power Plants

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Topics: Filters , Nuclear power stations , Tides , Water , Cooling , Safety , Design , Seas

Validation of the Moody and Henry–Fauske Critical Flow Models in apros Against Marviken Critical Flow Experiments

Milan Tesinsky

ASME J of Nuclear Rad Sci. October 2020, 6(4): 041102. doi: https://doi.org/10.1115/1.4046432

Abstract

View articletitled, Validation of the Moody and Henry–Fauske Critical Flow Models in <span class="small-caps">apros</span> Against Marviken Critical Flow Experiments

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Topics: Flow (Dynamics) , Discharge coefficient

The Sensitivity Analysis of the Core Lower Head Molten Pool Model Based on Variance Decomposition

ZhiGang Li, Wei Liu, PingZhou Ming, Ping An, Wei Lu, JunJie Pan

ASME J of Nuclear Rad Sci. October 2020, 6(4): 041103. doi: https://doi.org/10.1115/1.4047093

Abstract

View articletitled, The Sensitivity Analysis of the Core Lower Head Molten Pool Model Based on Variance Decomposition

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Topics: Sensitivity analysis

Noncontact Displacement Measurement of Nuclear Waste Canisters in a Geological Disposal by Using an Electromagnetic-Wave Approach

Mauro Cappelli, Vincenzo Surrenti

ASME J of Nuclear Rad Sci. October 2020, 6(4): 041104. doi: https://doi.org/10.1115/1.4047719

Abstract

View articletitled, Noncontact Displacement Measurement of Nuclear Waste Canisters in a Geological Disposal by Using an Electromagnetic-Wave Approach

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Topics: Cables , Displacement measurement , Radioactive wastes , Resolution (Optics) , Resonance , Sensors , Signals , Water , Wavelength , Waves

Organ Dose Calculations Using ICRP Adult Voxel Phantoms and TRIPOLI-4 Monte Carlo Code

Yi-Kang Lee

ASME J of Nuclear Rad Sci. October 2020, 6(4): 041105. doi: https://doi.org/10.1115/1.4046213

Abstract

View articletitled, Organ Dose Calculations Using ICRP Adult Voxel Phantoms and TRIPOLI-4 Monte Carlo Code

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Topics: Phantoms , Photons , Biological tissues , Electrons , Neutrons , Radiation (Physics)

ASME Boiler and Pressure Vessel Code Roadmap for Compact Heat Exchangers in High Temperature Reactors

Robert B. Keating, Suzanne P. McKillop, Todd Allen, Mark Anderson

ASME J of Nuclear Rad Sci. October 2020, 6(4): 041106. doi: https://doi.org/10.1115/1.4047113

Abstract

View articletitled, ASME Boiler and Pressure Vessel Code Roadmap for Compact Heat Exchangers in High Temperature Reactors

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Topics: Design , Diffusion (Physics) , Heat exchangers , High temperature , Reliability , Testing , Construction , ASME Standards , ASME Boiler and Pressure Vessel Code , Stress

A Novel Assessment of Delayed Neutron Detector Data in CANDU Reactors

Will Aylward, Christopher Wallace, Graeme West, Curtis McEwan

ASME J of Nuclear Rad Sci. October 2020, 6(4): 041107. doi: https://doi.org/10.1115/1.4046824

Abstract

View articletitled, A Novel Assessment of Delayed Neutron Detector Data in CANDU Reactors

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Topics: Fuels , Neutrons , Sensors , Noise control , Monitoring systems

Steam Condensation Heat Transfer During Initial Blow-Down Period of a Severe Nuclear Accident

Mahesh Kumar Yadav, Maneesh Punetha, Abhinav Bhanawat, Sameer Khandekar, Pavan K. Sharma

ASME J of Nuclear Rad Sci. October 2020, 6(4): 041108. doi: https://doi.org/10.1115/1.4046910

Abstract

View articletitled, Steam Condensation Heat Transfer During Initial Blow-Down Period of a Severe Nuclear Accident

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Topics: Accidents , Condensation , Heat flux , Heat transfer , Pressure , Steady state , Steam , Temperature , Transients (Dynamics) , Containment

Investigations on Effect of Lift and Wall Lubrication Forces on the Subcooled Flow Boiling

Sai Raja Gopal Vadlamudi, Arun K. Nayak

ASME J of Nuclear Rad Sci. October 2020, 6(4): 041109. doi: https://doi.org/10.1115/1.4048124

Abstract

View articletitled, Investigations on Effect of Lift and Wall Lubrication Forces on the Subcooled Flow Boiling

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Topics: Boiling , Bubbles , Flow (Dynamics) , Lift (Fluid dynamics) , Lubrication , Porosity , Subcooling , Turbulence , Heat flux

Criticality Characteristics and Sensitivity Analysis of Fukushima Debris Beds Containing MCCI Products

María Freiría López, Michael Buck, Jörg Starflinger

ASME J of Nuclear Rad Sci. October 2020, 6(4): 041110. doi: https://doi.org/10.1115/1.4047094

Abstract

View articletitled, Criticality Characteristics and Sensitivity Analysis of Fukushima Debris Beds Containing MCCI Products

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Topics: Concretes , Water , Fukushima nuclear disaster, Japan, 2011 , Vessels , Sensitivity analysis

Best-Estimate Plus Uncertainty Analysis of CANDU Fuel Reliability Using Manufacturing and Simulated Core Data

Jason J. Song, Paul K. Chan, Hugues W. Bonin, Mahesh Pandey

ASME J of Nuclear Rad Sci. October 2020, 6(4): 041111. doi: https://doi.org/10.1115/1.4047162

Abstract

View articletitled, Best-Estimate Plus Uncertainty Analysis of CANDU Fuel Reliability Using Manufacturing and Simulated Core Data

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Topics: Fuels , Manufacturing , Simulation , Transients (Dynamics) , Temperature , Uncertainty , Pressure

Analysis Methods for High Energy Line Break Jet Flows in Nuclear Power Plants

Marwan Charrouf, Storm Kauffman, Jin-Kyoo Yoon, Sang-Gyu Lee, Taejoon Kim

ASME J of Nuclear Rad Sci. October 2020, 6(4): 041112. doi: https://doi.org/10.1115/1.4047441

Abstract

View articletitled, Analysis Methods for High Energy Line Break Jet Flows in Nuclear Power Plants

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Topics: Computational fluid dynamics , Flow (Dynamics) , Jets , Nozzles , Nuclear power stations , Pipes , Pressure , Reflection , Resonance , Waves

Analysis of the Effect of Vessel Failure and Melt Release on Risk of Containment Failure Due to Ex-Vessel Steam Explosion in Nordic Boiling Water Reactor Using ROAAM+ Framework

Sergey Galushin, Dmitry Grishchenko, Pavel Kudinov

ASME J of Nuclear Rad Sci. October 2020, 6(4): 041113. doi: https://doi.org/10.1115/1.4047552

Abstract

View articletitled, Analysis of the Effect of Vessel Failure and Melt Release on Risk of Containment Failure Due to Ex-Vessel Steam Explosion in Nordic Boiling Water Reactor Using ROAAM+ Framework

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Topics: Boiling water reactors , Containment , Explosions , Failure , Steam , Vessels , Risk , Accidents , Uncertainty

Research Papers

Next Generation/Advanced Reactors

Effect of Pulsation and Acceleration of Liquid Metal Turbulent Flow Through a Horizontal Channel by Large Eddy Simulation

N. Satish, K. Venkatasubbaiah

ASME J of Nuclear Rad Sci. October 2020, 6(4): 041301. doi: https://doi.org/10.1115/1.4046259

Abstract

View articletitled, Effect of Pulsation and Acceleration of Liquid Metal Turbulent Flow Through a Horizontal Channel by Large Eddy Simulation

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Topics: Flow (Dynamics) , Heat transfer , Liquid metals , Reynolds number , Turbulence , Convection , Large eddy simulation

A Review of Circulating Voids and Gaseous Fission Product Behavior in Molten Salt Reactors

Terry Price, Zack Taylor, Ondrej Chvala

ASME J of Nuclear Rad Sci. October 2020, 6(4): 041302. doi: https://doi.org/10.1115/1.4046258

Abstract

View articletitled, A Review of Circulating Voids and Gaseous Fission Product Behavior in Molten Salt Reactors

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Topics: Bubbles , Fuels , Molten salt reactors , Porosity , Pressure , Nuclear fission , Flow (Dynamics) , Pumps

Xenon Behavior in Molten Salt Reactor Graphite

Terry J. Price, Ondrej Chvala, Zack Taylor

ASME J of Nuclear Rad Sci. October 2020, 6(4): 041303. doi: https://doi.org/10.1115/1.4046356

Abstract

View articletitled, Xenon Behavior in Molten Salt Reactor Graphite

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Topics: Graphite , Molten salt reactors , Diffusion (Physics) , Mass transfer

Role of the Nonrotating Decay Heat Removal Blower Pressure Loss in ALLEGRO Reactor

G. Mayer, A. Guba

ASME J of Nuclear Rad Sci. October 2020, 6(4): 041304. doi: https://doi.org/10.1115/1.4045805

Abstract

View articletitled, Role of the Nonrotating Decay Heat Removal Blower Pressure Loss in ALLEGRO Reactor

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Topics: Heat , Pressure , Transients (Dynamics) , Valves

Flame-Free Combustion of Radioactive and Hazardous Wastes in the Salt Melt

Vojtěch Galek, Jaroslav Stoklasa, Jan Hadrava, Roman Vokatý

ASME J of Nuclear Rad Sci. October 2020, 6(4): 041305. doi: https://doi.org/10.1115/1.4046911

Abstract

View articletitled, Flame-Free Combustion of Radioactive and Hazardous Wastes in the Salt Melt

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Topics: Combustion , Flames , Flue gases , Metals , Oxidation , Temperature , Radioisotopes , Hazardous wastes , Oxygen , Heavy metals

Radiation Science

Tensioned Metastable Fluid Detectors for Spectrometric Radon–Progeny Detection and AARST-NRPP Standard Qualification

Mitch P. Hemesath, Brian C. Archambault, Nathan M. Boyle, Rusi P. Taleyarkhan

ASME J of Nuclear Rad Sci. October 2020, 6(4): 042001. doi: https://doi.org/10.1115/1.4045691

Abstract

View articletitled, Tensioned Metastable Fluid Detectors for Spectrometric Radon–Progeny Detection and AARST-NRPP Standard Qualification

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Topics: Errors , Fluids , Pressure , Sensors , Temperature , Air flow , Algorithms , Testing , Radiation (Physics)

Investigation and Characterization of Gamma Radiation Shielding Capacity of Heavy Minerals-Based Composite Materials

Mohammad Asaduzzaman Chowdhury, Md. Bengir Ahmed Shuvho, Md Azizul Islam, Muhammad Borhan Uddin, Ruhul Amin Khan

ASME J of Nuclear Rad Sci. October 2020, 6(4): 042002. doi: https://doi.org/10.1115/1.4046357

Abstract

View articletitled, Investigation and Characterization of Gamma Radiation Shielding Capacity of Heavy Minerals-Based Composite Materials

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Topics: Composite materials , Gamma rays , Radiation (Physics) , Fourier transform infrared spectroscopy , Minerals

Characterization of Atmospheric Radiological Dispersion Alongside Risky Location Designation and Shelter House Proposition Around the Planned Rooppur Nuclear Power Plant

Afrida Fairuz, Md. Hossain Sahadath

ASME J of Nuclear Rad Sci. October 2020, 6(4): 042003. doi: https://doi.org/10.1115/1.4046670

Abstract

View articletitled, Characterization of Atmospheric Radiological Dispersion Alongside Risky Location Designation and Shelter House Proposition Around the Planned Rooppur Nuclear Power Plant

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Topics: Meteorology , Nuclear power stations , Plumes (Fluid dynamics) , Stability , Wind , Wind velocity , Sunlight

Technology Review

Current Status of Reactors Deployment and Small Modular Reactors Development in the World

I. Pioro, R. B. Duffey, P. L. Kirillov, N. Dort-Goltz

ASME J of Nuclear Rad Sci. October 2020, 6(4): 044001. doi: https://doi.org/10.1115/1.4047927

Abstract

View articletitled, Current Status of Reactors Deployment and Small Modular Reactors Development in the World

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Topics: Boiling water reactors , China , Construction , Design , Fuels , Licensing , Nuclear power , Nuclear power stations , Nuclear reactors , Pressurized water reactors

Guest Editorial

Special Section: Selected Papers from ICONE-27

Special Papers

Analysis on Critical Factors of Marine Organism Impacts on Water Intake Safety at Nuclear Power Plants

Validation of the Moody and Henry–Fauske Critical Flow Models in apros Against Marviken Critical Flow Experiments

The Sensitivity Analysis of the Core Lower Head Molten Pool Model Based on Variance Decomposition

Noncontact Displacement Measurement of Nuclear Waste Canisters in a Geological Disposal by Using an Electromagnetic-Wave Approach

Organ Dose Calculations Using ICRP Adult Voxel Phantoms and TRIPOLI-4 Monte Carlo Code

ASME Boiler and Pressure Vessel Code Roadmap for Compact Heat Exchangers in High Temperature Reactors

A Novel Assessment of Delayed Neutron Detector Data in CANDU Reactors

Steam Condensation Heat Transfer During Initial Blow-Down Period of a Severe Nuclear Accident

Investigations on Effect of Lift and Wall Lubrication Forces on the Subcooled Flow Boiling

Criticality Characteristics and Sensitivity Analysis of Fukushima Debris Beds Containing MCCI Products

Best-Estimate Plus Uncertainty Analysis of CANDU Fuel Reliability Using Manufacturing and Simulated Core Data

Analysis Methods for High Energy Line Break Jet Flows in Nuclear Power Plants

Analysis of the Effect of Vessel Failure and Melt Release on Risk of Containment Failure Due to Ex-Vessel Steam Explosion in Nordic Boiling Water Reactor Using ROAAM+ Framework

Research Papers

Next Generation/Advanced Reactors

Effect of Pulsation and Acceleration of Liquid Metal Turbulent Flow Through a Horizontal Channel by Large Eddy Simulation

A Review of Circulating Voids and Gaseous Fission Product Behavior in Molten Salt Reactors

Xenon Behavior in Molten Salt Reactor Graphite

Role of the Nonrotating Decay Heat Removal Blower Pressure Loss in ALLEGRO Reactor

Flame-Free Combustion of Radioactive and Hazardous Wastes in the Salt Melt

Radiation Science

Tensioned Metastable Fluid Detectors for Spectrometric Radon–Progeny Detection and AARST-NRPP Standard Qualification

Investigation and Characterization of Gamma Radiation Shielding Capacity of Heavy Minerals-Based Composite Materials

Characterization of Atmospheric Radiological Dispersion Alongside Risky Location Designation and Shelter House Proposition Around the Planned Rooppur Nuclear Power Plant

Technology Review

Current Status of Reactors Deployment and Small Modular Reactors Development in the World

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