Volume 5 Issue 4 | ASME J. of Nuclear Rad Sci.

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Volume 5, Issue 4

October 2019

ISSN 2332-8983

EISSN 2332-8975

In Memoriam

In Memoriam: Geoff Hewitt

Michael Bluck, Ph.D., Dr., Igor Pioro, Ph.D., Dr. Tech. Sc., P.Eng.,, Simon Walker, Ph.D., Dr.

ASME J of Nuclear Rad Sci. October 2019, 5(4): 040101. doi: https://doi.org/10.1115/1.4043661

Extract

View articletitled, In Memoriam: Geoff Hewitt

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Topics: Engineering teachers , Engineers , Heat transfer , Multiphase flow , Two-phase flow , Boiling , Design , Heat exchangers

Research Papers

Analyses of the Associated Technical and Economic Risks of the Simple and Intercooled Brayton Helium Recuperated Gas Turbine Cycles for Generation IV Nuclear Power Plants

Arnold Gad-Briggs, Pericles Pilidis, Theoklis Nikolaidis

ASME J of Nuclear Rad Sci. October 2019, 5(4): 041201. doi: https://doi.org/10.1115/1.4042116

Abstract

View articletitled, Analyses of the Associated Technical and Economic Risks of the Simple and Intercooled Brayton Helium Recuperated Gas Turbine Cycles for Generation IV Nuclear Power Plants

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Topics: Cycles , Helium , Nuclear power stations , Temperature , Pressure , Financial risk , Design , Risk , Compressors

Research on a Transonic Supercritical Carbon Dioxide Centrifugal Turbine

Zehai Yang, Dan Luo, Diangui Huang

ASME J of Nuclear Rad Sci. October 2019, 5(4): 041202. doi: https://doi.org/10.1115/1.4043295

Abstract

View articletitled, Research on a Transonic Supercritical Carbon Dioxide Centrifugal Turbine

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Topics: Blades , Computer simulation , Design , Flow (Dynamics) , Pressure , Rotors , Turbines , Nozzles , Supercritical carbon dioxide

Experimental Demonstration of Decay Heat Removal by Submerged Feeders in a Full-Scale Test Facility of a Natural Circulation Boiling Water Reactor

A. K. Nayak, Mukesh Kumar, Sumit V. Prasad, V. Jain, D. K. Chandraker

ASME J of Nuclear Rad Sci. October 2019, 5(4): 041203. doi: https://doi.org/10.1115/1.4042852

Abstract

View articletitled, Experimental Demonstration of Decay Heat Removal by Submerged Feeders in a Full-Scale Test Facility of a Natural Circulation Boiling Water Reactor

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Topics: Heat , Test facilities , Water , Cavities , Earthquakes , Heat sinks , Boiling water reactors , Flow (Dynamics) , Fukushima nuclear disaster, Japan, 2011 , Fracture (Materials)

Effect of Steam Temperature and Pressure on the Oxidation of Potential Coating Alloy FeCrAl for Supercritical Water-Cooled Reactor Application

Bingjie Xiao, Xiao Huang, Qi Yang, Prakash Patnaik

ASME J of Nuclear Rad Sci. October 2019, 5(4): 041204. doi: https://doi.org/10.1115/1.4042500

Abstract

View articletitled, Effect of Steam Temperature and Pressure on the Oxidation of Potential Coating Alloy FeCrAl for Supercritical Water-Cooled Reactor Application

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Topics: Alloys , Coatings , Oxidation , Pressure , Steam , Superheating , Temperature , Water , Weight (Mass) , High temperature

Experimental Demonstration of Safety During Extended Station Blackout in an Integral Test Loop of a Natural Circulation Boiling Water Reactor

A. K. Nayak, Mukesh Kumar, A. K. Vishnoi, Vikas Jain, D. K. Chandraker

ASME J of Nuclear Rad Sci. October 2019, 5(4): 041205. doi: https://doi.org/10.1115/1.4043198

Abstract

View articletitled, Experimental Demonstration of Safety During Extended Station Blackout in an Integral Test Loop of a Natural Circulation Boiling Water Reactor

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Topics: Boiling water reactors , Condensers (steam plant) , Coolants , Design , Flow (Dynamics) , Heat , Pressure , Safety , Temperature , Test facilities

Experimental Investigation of Melt Coolability and Ablation Behavior of Oxidic Sacrificial Material at Prototypic Conditions in Scaled Down Core Catcher

Samyak S. Munot, Ganesh V, Parimal P. Kulkarni, Arun K. Nayak

ASME J of Nuclear Rad Sci. October 2019, 5(4): 041206. doi: https://doi.org/10.1115/1.4043106

Abstract

View articletitled, Experimental Investigation of Melt Coolability and Ablation Behavior of Oxidic Sacrificial Material at Prototypic Conditions in Scaled Down Core Catcher

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Topics: Ablation (Vaporization technology) , Bricks , Cavities , Temperature , Thermocouples , Vessels , Water , Heat , Accidents , Floods

Gas Turbine Arekret-Cycle Simulation Modeling for Training and Educational Purposes

Emmanuel O. Osigwe, Pericles Pilidis, Theoklis Nikolaidis, Suresh Sampath

ASME J of Nuclear Rad Sci. October 2019, 5(4): 041207. doi: https://doi.org/10.1115/1.4043681

Abstract

View articletitled, Gas Turbine Arekret-Cycle Simulation Modeling for Training and Educational Purposes

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Topics: Closed-cycle gas turbines , Compressors , Computer simulation , Cycles , Design , Engines , Flow (Dynamics) , Fluids , Gas turbines , Pressure

Application of Fractional Scaling Analysis for Development and Design of Integral Effects Test Facility

Milorad B. Dzodzo, Francesco Oriolo, Walter Ambrosini, Marco Ricotti, Davor Grgic, Roberta Ferri, Andrea Achilli, Fosco Bianchi, Paride Meloni

ASME J of Nuclear Rad Sci. October 2019, 5(4): 041208. doi: https://doi.org/10.1115/1.4042496

Abstract

View articletitled, Application of Fractional Scaling Analysis for Development and Design of Integral Effects Test Facility

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Topics: Containment vessels , Engineering prototypes , Pressure , Reactor vessels , Test facilities , Transients (Dynamics) , Water , Design , Heat , Containment

Supercritical Carbon Dioxide Centripetal Compressor—Aerodynamic Design and Analysis of Off Design Conditions

Xuefei Du, Dengtao Yu, Dan Luo, Diangui Huang

ASME J of Nuclear Rad Sci. October 2019, 5(4): 041209. doi: https://doi.org/10.1115/1.4043846

Abstract

View articletitled, Supercritical Carbon Dioxide Centripetal Compressor—Aerodynamic Design and Analysis of Off Design Conditions

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Topics: Compressors , Design , Flow (Dynamics) , Pressure , Supercritical carbon dioxide

Molten Salt Reactor Xenon Analysis: Review and Decomposition

Terry J. Price, Ondrej Chvala, Zack Taylor

ASME J of Nuclear Rad Sci. October 2019, 5(4): 041210. doi: https://doi.org/10.1115/1.4043813

Abstract

View articletitled, Molten Salt Reactor Xenon Analysis: Review and Decomposition

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

Computational Fluid Dynamics Simulation of Flow-Mixing and Heat Transfer in 4 × 4 Rod Bundle With a Twist-Vane Spacer Grid

Ganesh Lal Kumawat, Anuj Kumar Kansal, Naresh Kumar Maheshwari, Avaneesh Sharma

ASME J of Nuclear Rad Sci. October 2019, 5(4): 041301. doi: https://doi.org/10.1115/1.4042120

Abstract

View articletitled, Computational Fluid Dynamics Simulation of Flow-Mixing and Heat Transfer in 4 × 4 Rod Bundle With a Twist-Vane Spacer Grid

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Topics: Computational fluid dynamics , Flow (Dynamics) , Fuel rods , Heat transfer , Simulation , Turbulence

Neutronic and Thermo-Hydraulic Analyses of Water-Cooled Blanket Based on Pressurized/Supercritical Water Conditions for CFETR

Jie Cheng, Yingwei Wu, G. H. Su, Suizheng Qiu, Wenxi Tian

ASME J of Nuclear Rad Sci. October 2019, 5(4): 041302. doi: https://doi.org/10.1115/1.4042364

Abstract

View articletitled, Neutronic and Thermo-Hydraulic Analyses of Water-Cooled Blanket Based on Pressurized/Supercritical Water Conditions for CFETR

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Topics: Water , Flow (Dynamics) , Design , Simulation

Numerical Analysis of Slotted Airfoil Fins for Printed Circuit Heat Exchanger in S-CO₂ Brayton Cycle

Xiao Long Li, G. H. Tang, Yuan Hong Fan, Dan Lei Yang, Si Qi Wang

ASME J of Nuclear Rad Sci. October 2019, 5(4): 041303. doi: https://doi.org/10.1115/1.4043098

Abstract

View articletitled, Numerical Analysis of Slotted Airfoil Fins for Printed Circuit Heat Exchanger in S-CO<sub>2</sub> Brayton Cycle

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Topics: Fins , Flow (Dynamics) , Heat transfer , Supercritical carbon dioxide , Heat exchangers , Circuits , Brayton cycle

A Study of Transverse Buckling Effect on the Characteristics of Nuclides Burnup Wave in a Fast Neutron Multiplying Media

Manish Kumar, Om Pal Singh

ASME J of Nuclear Rad Sci. October 2019, 5(4): 041401. doi: https://doi.org/10.1115/1.4043294

Abstract

View articletitled, A Study of Transverse Buckling Effect on the Characteristics of Nuclides Burnup Wave in a Fast Neutron Multiplying Media

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Topics: Neutrons , Waves , Nuclides , Buckling , Leakage , Transients (Dynamics)

Verification and Validation of SuperMC3.2 Using VENUS-3 Benchmark Experiments

I. K. Baidoo, J. Zou, B. Li, J. Song, B. Wu, Q. Yang, Z. Zhao

ASME J of Nuclear Rad Sci. October 2019, 5(4): 041402. doi: https://doi.org/10.1115/1.4043100

Abstract

View articletitled, Verification and Validation of SuperMC3.2 Using VENUS-3 Benchmark Experiments

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Topics: Atoms , Displacement , Dosimetry , Fluence (Radiation measurement) , Fuels , Geometry , Iron , Manufacturing , Modeling , Neutron flux

Analysis of Shutdown System Effectiveness in the Canadian Super Critical Water Reactor Using Coupled Thermal Hydraulics and Three-Dimensional Neutron Kinetics

David William Hummel, David Raymond Novog

ASME J of Nuclear Rad Sci. October 2019, 5(4): 041403. doi: https://doi.org/10.1115/1.4042597

Abstract

View articletitled, Analysis of Shutdown System Effectiveness in the Canadian Super Critical Water Reactor Using Coupled Thermal Hydraulics and Three-Dimensional Neutron Kinetics

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Topics: Blades , Coolants , Flow (Dynamics) , Fuels , Neutrons , Supercritical water reactors , Thermal hydraulics , Transients (Dynamics) , Water , Delays

Measurements of Adhesion Force Between a Single Silver Particle Interacting With Hastelloy X and Inconel 617

Naphtali M. Mokgalapa, Tushar K. Ghosh, Robert V. Tompson, Sudarshan K. Loyalka

ASME J of Nuclear Rad Sci. October 2019, 5(4): 041501. doi: https://doi.org/10.1115/1.4042706

Abstract

View articletitled, Measurements of Adhesion Force Between a Single Silver Particle Interacting With Hastelloy X and Inconel 617

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Topics: Adhesion , Particulate matter , Silver

Evaluation of Dump Tank Coolability in PHWRs During Late-Phase Severe Accident

Pradeep Pandey, Parimal P. Kulkarni, Arun Nayak, Sumit V. Prasad

ASME J of Nuclear Rad Sci. October 2019, 5(4): 041601. doi: https://doi.org/10.1115/1.4043108

Abstract

View articletitled, Evaluation of Dump Tank Coolability in PHWRs During Late-Phase Severe Accident

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Topics: Accidents , Heat , Heavy water reactors , Temperature , Vessels , Water , Design , Boiling , Nuclear power stations , Failure

Calculation of Evaporation From Fukushima Nuclear Power Plant Spent Fuel Pools

Mirza M. Shah

ASME J of Nuclear Rad Sci. October 2019, 5(4): 041602. doi: https://doi.org/10.1115/1.4043847

Abstract

View articletitled, Calculation of Evaporation From Fukushima Nuclear Power Plant Spent Fuel Pools

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Topics: Evaporation , Fukushima nuclear disaster, Japan, 2011 , Nuclear power stations , Spent nuclear fuels , Heat , Fuels

A Study on Onset of Liquid Entrainment in Low Pressure Depressurization System of Advanced Passive Pressurized Water Reactors

Jun Liao, Katsuhiro Ohkawa, William L. Brown, Richard F. Wright

ASME J of Nuclear Rad Sci. October 2019, 5(4): 041701. doi: https://doi.org/10.1115/1.4042796

Abstract

View articletitled, A Study on Onset of Liquid Entrainment in Low Pressure Depressurization System of Advanced Passive Pressurized Water Reactors

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Topics: Flow (Dynamics) , Pipes , Pressure , Pressurized water reactors , Stratified flow , Water , Steam

On One Imperfection Estimation Method for Thin Shell Buckling in the Design Code RCC-MR

Ashok Kumar, Anindya Chatterjee

ASME J of Nuclear Rad Sci. October 2019, 5(4): 042001. doi: https://doi.org/10.1115/1.4042117

Abstract

View articletitled, On One Imperfection Estimation Method for Thin Shell Buckling in the Design Code RCC-MR

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Topics: Buckling , Shells , Stress , Design

Suite for Smooth Particle Hydrodynamic Code Relevant to Spherical Plasma Liner Formation and Implosion

Kevin Schillo, Jason Cassibry, Mitchell Rodriguez, Seth Thompson

ASME J of Nuclear Rad Sci. October 2019, 5(4): 042201. doi: https://doi.org/10.1115/1.4042710

Abstract

View articletitled, Suite for Smooth Particle Hydrodynamic Code Relevant to Spherical Plasma Liner Formation and Implosion

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Topics: Heat conduction , Particulate matter , Plasmas (Ionized gases) , Pressure , Radiation (Physics) , Shock (Mechanics) , Simulation , Temperature , Viscosity , Vortices

Analysis of Loss of Heat Sink for ITER Divertor Cooling System Using Modified RELAP/SCDAPSIM/MOD 4.0

S. P. Saraswat, D. Ray, P. Munshi, C. Allison

ASME J of Nuclear Rad Sci. October 2019, 5(4): 042202. doi: https://doi.org/10.1115/1.4042707

Abstract

View articletitled, Analysis of Loss of Heat Sink for ITER Divertor Cooling System Using Modified RELAP/SCDAPSIM/MOD 4.0

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Topics: Accidents , Coolants , Cooling systems , Design , Heat , Heat sinks , Modeling , Plasmas (Ionized gases) , Pressure , Sprays

Technical Brief

Gamma and X-Ray Shielding Properties of Various Types of Steels

H. C. Manjunatha, L. Seenappa

ASME J of Nuclear Rad Sci. October 2019, 5(4): 044501. doi: https://doi.org/10.1115/1.4043814

Abstract

View articletitled, Gamma and X-Ray Shielding Properties of Various Types of Steels

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Topics: Atomic number , Gamma rays , Steel , X-rays

In Memoriam

In Memoriam: Geoff Hewitt

Research Papers

Analyses of the Associated Technical and Economic Risks of the Simple and Intercooled Brayton Helium Recuperated Gas Turbine Cycles for Generation IV Nuclear Power Plants

Research on a Transonic Supercritical Carbon Dioxide Centrifugal Turbine

Experimental Demonstration of Decay Heat Removal by Submerged Feeders in a Full-Scale Test Facility of a Natural Circulation Boiling Water Reactor

Effect of Steam Temperature and Pressure on the Oxidation of Potential Coating Alloy FeCrAl for Supercritical Water-Cooled Reactor Application

Experimental Demonstration of Safety During Extended Station Blackout in an Integral Test Loop of a Natural Circulation Boiling Water Reactor

Experimental Investigation of Melt Coolability and Ablation Behavior of Oxidic Sacrificial Material at Prototypic Conditions in Scaled Down Core Catcher

Gas Turbine Arekret-Cycle Simulation Modeling for Training and Educational Purposes

Application of Fractional Scaling Analysis for Development and Design of Integral Effects Test Facility

Supercritical Carbon Dioxide Centripetal Compressor—Aerodynamic Design and Analysis of Off Design Conditions

Molten Salt Reactor Xenon Analysis: Review and Decomposition

Computational Fluid Dynamics Simulation of Flow-Mixing and Heat Transfer in 4 × 4 Rod Bundle With a Twist-Vane Spacer Grid

Neutronic and Thermo-Hydraulic Analyses of Water-Cooled Blanket Based on Pressurized/Supercritical Water Conditions for CFETR

Numerical Analysis of Slotted Airfoil Fins for Printed Circuit Heat Exchanger in S-CO₂ Brayton Cycle

A Study of Transverse Buckling Effect on the Characteristics of Nuclides Burnup Wave in a Fast Neutron Multiplying Media

Verification and Validation of SuperMC3.2 Using VENUS-3 Benchmark Experiments

Analysis of Shutdown System Effectiveness in the Canadian Super Critical Water Reactor Using Coupled Thermal Hydraulics and Three-Dimensional Neutron Kinetics

Measurements of Adhesion Force Between a Single Silver Particle Interacting With Hastelloy X and Inconel 617

Evaluation of Dump Tank Coolability in PHWRs During Late-Phase Severe Accident

Calculation of Evaporation From Fukushima Nuclear Power Plant Spent Fuel Pools

A Study on Onset of Liquid Entrainment in Low Pressure Depressurization System of Advanced Passive Pressurized Water Reactors

On One Imperfection Estimation Method for Thin Shell Buckling in the Design Code RCC-MR

Suite for Smooth Particle Hydrodynamic Code Relevant to Spherical Plasma Liner Formation and Implosion

Analysis of Loss of Heat Sink for ITER Divertor Cooling System Using Modified RELAP/SCDAPSIM/MOD 4.0

Technical Brief

Gamma and X-Ray Shielding Properties of Various Types of Steels

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