Volume 7 Issue 3 | ASME J. of Nuclear Rad Sci.

Review Articles

A Comparative Study on Severe Accident Phenomena Related to Melt Progression in Sodium Fast Reactors and Pressurized Water Reactors

Andrea Bachrata, Fréderic Bertrand, Nathalie Marie, Fréderic Serre

ASME J of Nuclear Rad Sci. July 2021, 7(3): 030801. doi: https://doi.org/10.1115/1.4047921

View articletitled, A Comparative Study on Severe Accident Phenomena Related to Melt Progression in Sodium Fast Reactors and Pressurized Water Reactors

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Topics: Accidents , Pressurized water reactors , Sodium fast reactors , Safety , Vessels

Heat Transfer in Supercritical Fluids: A Review

Kapil Bodkha, N. K. Maheshwari

ASME J of Nuclear Rad Sci. July 2021, 7(3): 030802. doi: https://doi.org/10.1115/1.4048898

Abstract

View articletitled, Heat Transfer in Supercritical Fluids: A Review

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Topics: Carbon dioxide , Fluids , Heat transfer , Supercritical fluids , Temperature , Water , Pressure , Heat flux

Research Papers

Next Generation/Advanced Reactors

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

ASME J of Nuclear Rad Sci. July 2021, 7(3): 031301. doi: https://doi.org/10.1115/1.4048903

Abstract

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

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

Passive and Walk-Away Safe Small and Microreactors for Electricity Generation and Production of Process Heat for Industrial Uses

Mohamed S. El-Genk, Timothy M. Schriener, Luis M. Palomino

ASME J of Nuclear Rad Sci. July 2021, 7(3): 031302. doi: https://doi.org/10.1115/1.4047920

Abstract

View articletitled, Passive and Walk-Away Safe Small and Microreactors for Electricity Generation and Production of Process Heat for Industrial Uses

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Topics: Electric power generation , Fuels , Heat , Neutrons , Safety , Sodium , Vessels , Design , Metals , Steel

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

Abstract

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

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

GTAW Welded Inconel 625 Alloy Fuel Cladding for the Canadian SCWR: Microstructure and Mechanical Property Characterization

Cota-Sanchez German, Xiao Lin

ASME J of Nuclear Rad Sci. July 2021, 7(3): 031304. doi: https://doi.org/10.1115/1.4049278

Abstract

View articletitled, GTAW Welded Inconel 625 Alloy Fuel Cladding for the Canadian SCWR: Microstructure and Mechanical Property Characterization

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Topics: Heat , Welding , Cladding systems (Building) , Fuels , Alloys , Supercritical water reactors , Mechanical properties , Gas tungsten arc welding , Welded joints

Thermal Hydraulics and CFD

Heat Transfer and Hydraulic Resistance in Turbulent Flow in Vertical Round Tubes at Supercritical Pressures—Part 1: Results From Numerical Simulations Using Algebraic Turbulent Viscosity Models

Georgy G. Yankov, Vladimir A. Kurganov, Yury A. Zeigarnik, Irina V. Maslakova

ASME J of Nuclear Rad Sci. July 2021, 7(3): 031401. doi: https://doi.org/10.1115/1.4047042

Abstract

View articletitled, Heat Transfer and Hydraulic Resistance in Turbulent Flow in Vertical Round Tubes at Supercritical Pressures—Part 1: Results From Numerical Simulations Using Algebraic Turbulent Viscosity Models

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Topics: Flow (Dynamics) , Heat transfer , Turbulence , Viscosity , Buoyancy , Algebra , Computer simulation , Pressure , Carbon dioxide

Heat Transfer and Hydraulic Resistance in Turbulent Flow in Vertical Round Tubes at Supercritical Pressures—Part II: Results From Numerical Simulation With Differential Turbulent Viscosity Models

Georgy G. Yankov, Vladimir A. Kurganov, Yury A. Zeigarnik, Irina V. Maslakova

ASME J of Nuclear Rad Sci. July 2021, 7(3): 031402. doi: https://doi.org/10.1115/1.4047043

Abstract

View articletitled, Heat Transfer and Hydraulic Resistance in Turbulent Flow in Vertical Round Tubes at Supercritical Pressures—Part II: Results From Numerical Simulation With Differential Turbulent Viscosity Models

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Topics: Heat transfer , Turbulence , Flow (Dynamics) , Viscosity , Coolants

Optimization of the PGV-1000MKO Steam Generator Using Computation Fluid Dynamics

Vasilii Volkov, Luka Golibrodo, Alexey Krutikov, Oleg Kudryavtsev, Yurii Nadinskii, Alexander Skibin, Vladimir Sotskov

ASME J of Nuclear Rad Sci. July 2021, 7(3): 031403. doi: https://doi.org/10.1115/1.4048234

Abstract

View articletitled, Optimization of the PGV-1000MKO Steam Generator Using Computation Fluid Dynamics

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Topics: Flow (Dynamics) , Nozzles , Steam , Evaporation , Boilers , Optimization

Supercritical Water Choking Flow Experiments Through a Convergent-Divergent Test Section

A. Teyssedou, A. Muftuoglu, A. Hidouche

ASME J of Nuclear Rad Sci. July 2021, 7(3): 031404. doi: https://doi.org/10.1115/1.4048009

Abstract

View articletitled, Supercritical Water Choking Flow Experiments Through a Convergent-Divergent Test Section

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Topics: Flow (Dynamics) , Pressure , Temperature , Water , Fluids

Forced Convective Boiling in a Vertical Annular Test Section With Seawater Coolant

Zayed Ahmed, Seth Eckels, Steven J. Eckels, Hitesh Bindra

ASME J of Nuclear Rad Sci. July 2021, 7(3): 031405. doi: https://doi.org/10.1115/1.4049280

Abstract

View articletitled, Forced Convective Boiling in a Vertical Annular Test Section With Seawater Coolant

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Topics: Boiling , Bubbles , Heat transfer , Heat transfer coefficients , Seawater , Subcooling , Coolants , Wall temperature , Flow (Dynamics) , Temperature

Design of Condensation Heat Transfer Experiment to Evaluate Scaling Distortion in Small Modular Reactor Safety Analysis

Palash K. Bhowmik, J. P. Schlegel, V. Kalra, C. Mills, S. Usman

ASME J of Nuclear Rad Sci. July 2021, 7(3): 031406. doi: https://doi.org/10.1115/1.4050211

Abstract

View articletitled, Design of Condensation Heat Transfer Experiment to Evaluate Scaling Distortion in Small Modular Reactor Safety Analysis

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Topics: Condensation , Cooling , Design , Flow (Dynamics) , Heat transfer , Steam , Test facilities , Temperature , Pressure , Water

Reactor Physics

Determination of CR-39 and LR-115 Type II Mean Critical Angle of Etching Using a New Monte Carlo Code

H. Harrass, A. Talbi, R. Touti

ASME J of Nuclear Rad Sci. July 2021, 7(3): 031501. doi: https://doi.org/10.1115/1.4049343

Abstract

View articletitled, Determination of CR-39 and LR-115 Type II Mean Critical Angle of Etching Using a New Monte Carlo Code

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Topics: Alpha particles , Etching , Sensors

Canonical Implementation of Simplified Spherical Harmonics (SP_L) in the Neutron Diffusion Code AZNHEX

Guillermo Muñoz-Peña, Edmundo del Valle Gallegos, Armando Gomez-Torres

ASME J of Nuclear Rad Sci. July 2021, 7(3): 031502. doi: https://doi.org/10.1115/1.4049277

Abstract

View articletitled, Canonical Implementation of Simplified Spherical Harmonics (SPL) in the Neutron Diffusion Code AZNHEX

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Topics: Approximation , Diffusion (Physics) , Neutrons

Nuclear Fuels/Cycles and Materials

Effect of Sequential Helium and Nickel Ion Implantation on the Nano-Indentation Hardness of X750 Alloy

Maisaa N. Tawfeeq, Robert J. Klassen

ASME J of Nuclear Rad Sci. July 2021, 7(3): 031601. doi: https://doi.org/10.1115/1.4049095

Abstract

View articletitled, Effect of Sequential Helium and Nickel Ion Implantation on the Nano-Indentation Hardness of X750 Alloy

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Topics: Alloys , Helium , Ion implantation , Temperature , Nanoindentation , Bubbles , Hardening , Nickel , Heat , Damage

Experimental and Numerical Investigation of Solidification of Gallium in an Initially Emptied Horizontal Pipe Flow

Shawn Somers-Neal, Alex Pegarkov, Edgar Matida, Vinh Tang, Tarik Kaya

ASME J of Nuclear Rad Sci. July 2021, 7(3): 031602. doi: https://doi.org/10.1115/1.4049096

Abstract

View articletitled, Experimental and Numerical Investigation of Solidification of Gallium in an Initially Emptied Horizontal Pipe Flow

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Topics: Gallium , Metals , Pipes , Solidification , Temperature , Computer simulation , Reynolds number , Flow (Dynamics) , Wall temperature

Pressurized Water Reactor Mixed Oxide/UO₂ Transient Benchmark Calculations Using Monte Carlo Serpent 2 Code and Open Nodal Core Simulator ADPRES

Muhammad Imron, Donny Hartanto

ASME J of Nuclear Rad Sci. July 2021, 7(3): 031603. doi: https://doi.org/10.1115/1.4048764

Abstract

View articletitled, Pressurized Water Reactor Mixed Oxide/UO2 Transient Benchmark Calculations Using Monte Carlo Serpent 2 Code and Open Nodal Core Simulator ADPRES

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Topics: Boron , Coordinate measuring machines , Cross section (Physics) , Fuels , Manufacturing , Pressurized water reactors , Transients (Dynamics) , Temperature , Diffusion (Physics) , Geometry

Plant Systems, O&M, and Life Cycle

Deuterium Ingress at the Rolled Joints in CANDU Reactors: Where Does It Come From and How Can It Be Reduced?

S. T. Langille, C. E. Coleman, G. A. McRae

ASME J of Nuclear Rad Sci. July 2021, 7(3): 031801. doi: https://doi.org/10.1115/1.4048313

Abstract

View articletitled, Deuterium Ingress at the Rolled Joints in CANDU Reactors: Where Does It Come From and How Can It Be Reduced?

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Topics: Hydrogen , Pressure , Yttrium , Zirconium , Stainless steel , Fittings

Numerical Modeling and Experimental Validation of a Supercritical CO₂-Lubricated Hydrodynamic Journal Bearing

Nathan Colgan, Ken Cragin, Jeffrey Breedlove, Gregory Nellis, Mark Anderson

ASME J of Nuclear Rad Sci. July 2021, 7(3): 031802. doi: https://doi.org/10.1115/1.4049724

Abstract

View articletitled, Numerical Modeling and Experimental Validation of a Supercritical CO2-Lubricated Hydrodynamic Journal Bearing

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Topics: Bearings , Pressure , Temperature , Computer simulation , Fluids

RAW Management and Decommissioning

Numerical Simulation of Container Breach and Airborne Release of Solids Due to Mechanical Insults

David L. Y. Louie, San Le, Lindsay N. Gilkey

ASME J of Nuclear Rad Sci. July 2021, 7(3): 031901. doi: https://doi.org/10.1115/1.4050212

Abstract

View articletitled, Numerical Simulation of Container Breach and Airborne Release of Solids Due to Mechanical Insults

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Topics: Containers , Damage , Microscale devices , Simulation , Solids , Forklifts , Accidents , Fracture (Materials)

Radiation Science

Radiological Risk Assessment of Radon Gas in Bricks Samples in Iraq

Ali Abid Abojassim

ASME J of Nuclear Rad Sci. July 2021, 7(3): 032001. doi: https://doi.org/10.1115/1.4049051

Abstract

View articletitled, Radiological Risk Assessment of Radon Gas in Bricks Samples in Iraq

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Topics: Bricks , Uranium , Radium , Risk , Radiation (Physics) , Cancer , Risk assessment

Safety Analysis of Indonesia's Multipurpose Reactor During Irradiation of Natural UO₂ Pin Target at Power Ramp Test Facility

Octaviana Erawati Fadli, Azizul Khakim, S. Suharyana, A. Suparmi

ASME J of Nuclear Rad Sci. July 2021, 7(3): 032002. doi: https://doi.org/10.1115/1.4048904

Abstract

View articletitled, Safety Analysis of Indonesia's Multipurpose Reactor During Irradiation of Natural UO2 Pin Target at Power Ramp Test Facility

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Topics: Irradiation (Radiation exposure) , Safety , Neutron flux , Fuels , Test facilities

Photodegradation of Molecular Iodine on SiO₂ Particles: Influence of Temperature and Relative Humidity

A. Figueiredo, R. S. Strekowski, L. Bosland, A. Durand, H. Wortham

ASME J of Nuclear Rad Sci. July 2021, 7(3): 032003. doi: https://doi.org/10.1115/1.4048846

Abstract

View articletitled, Photodegradation of Molecular Iodine on SiO2 Particles: Influence of Temperature and Relative Humidity

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Topics: Particulate matter , Temperature , Desorption

Guided Waves Measurement Techniques in Pitch–Catch Configuration

Francesco Cordella, Francesco Bertoncini, Mauro Cappelli

ASME J of Nuclear Rad Sci. July 2021, 7(3): 032004. doi: https://doi.org/10.1115/1.4049345

Abstract

View articletitled, Guided Waves Measurement Techniques in Pitch–Catch Configuration

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Topics: Waves , Pipes , Signals , Cylinders

Technical Briefs

Radioactivity and Elements Measurements From Lagoon of Cocody Area District of Abidjan (Côte d'Ivoire)

Alfred Djoman Djama Agbo, Joseph Aka N'Gouan, Sévérin Goulizan Bi, Jean Claude Olkalé Brigui, Pierre Claver Konin Kakou

ASME J of Nuclear Rad Sci. July 2021, 7(3): 034501. doi: https://doi.org/10.1115/1.4048121

Abstract

View articletitled, Radioactivity and Elements Measurements From Lagoon of Cocody Area District of Abidjan (Côte d'Ivoire)

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Topics: Pollution , Radioactivity , Radioisotopes , Water , Heavy metals , Calibration , Diseases , Gamma ray spectrometry

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

Abstract

View articletitled, 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

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

Modeling and Simulation of Subcooled Coolant Loss Through Circumferential Pipe Leakage

Sandip Ghosh, Samir Kumar Saha

ASME J of Nuclear Rad Sci. July 2021, 7(3): 034503. doi: https://doi.org/10.1115/1.4048477

Abstract

View articletitled, Modeling and Simulation of Subcooled Coolant Loss Through Circumferential Pipe Leakage

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Topics: Flow (Dynamics) , Leakage , Pipes , Simulation , Subcooling , Flashing , Coolants , Fracture (Materials) , Modeling , Vapors

Development and Verification of Multiphysical Coupling Calculation Code for Typical Pressured Water Reactor Core

Zhigang Li, Ping An, Junjie Pan, Wei Liu, Wei Lu, Shenglong Qiang

ASME J of Nuclear Rad Sci. July 2021, 7(3): 034504. doi: https://doi.org/10.1115/1.4048027

Abstract

View articletitled, Development and Verification of Multiphysical Coupling Calculation Code for Typical Pressured Water Reactor Core

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Topics: Dynamics (Mechanics) , Fuels , Neutrons , Pressurized water reactors , Spacetime , Temperature , Transients (Dynamics) , Water , Cylinders , Computational methods

Serpent and Monte Carlo Continuous Energy Burnup Code Comparison for Neutronics Calculations of the European Lead-Cooled Fast Reactor

L. C. Juárez, J. I. Torres, J. L. François

ASME J of Nuclear Rad Sci. July 2021, 7(3): 034505. doi: https://doi.org/10.1115/1.4049714

Abstract

View articletitled, Serpent and Monte Carlo Continuous Energy Burnup Code Comparison for Neutronics Calculations of the European Lead-Cooled Fast Reactor

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Topics: Coolants , Density , Fast neutron reactors , Fuels , Neutrons , Cycles , Temperature , Modeling

Feasibility Study on the In-Service Testing Program Plan for Safety-Related Dampers of Advanced Power Reactor-1400

Shincheul Kang, Chan Park, Kyungho Lee, Sungho Lee

ASME J of Nuclear Rad Sci. July 2021, 7(3): 034506. doi: https://doi.org/10.1115/1.4050094

Abstract

View articletitled, Feasibility Study on the In-Service Testing Program Plan for Safety-Related Dampers of Advanced Power Reactor-1400

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Topics: Dampers , In-service testing , Safety , HVAC equipment

CANDU-Like Features in Emerging Small Modular Reactor Designs

Esam M. A. Hussein

ASME J of Nuclear Rad Sci. July 2021, 7(3): 034507. doi: https://doi.org/10.1115/1.4050477

Abstract

View articletitled, CANDU-Like Features in Emerging Small Modular Reactor Designs

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Topics: Fuels , Small modular reactors , Water , Coolants , Drainage , Heat sinks , Design , Construction , Lithium , Heat

Small Modular Reactors: Learning From the Past

Esam M. A. Hussein

ASME J of Nuclear Rad Sci. July 2021, 7(3): 034508. doi: https://doi.org/10.1115/1.4050478

Abstract

View articletitled, Small Modular Reactors: Learning From the Past

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Topics: Coolants , Fast neutron reactors , Fuels , Gas cooled reactors , High temperature , Liquid metals , Molten salt reactors , Pressurized water reactors , Small modular reactors , Licensing

Issues

Review Articles

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Next Generation/Advanced Reactors

Thermal Hydraulics and CFD

Reactor Physics

Nuclear Fuels/Cycles and Materials

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RAW Management and Decommissioning

Radiation Science

Technical Briefs

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