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Journal Articles

The Effect of Flow Channel Geometry on Thermomechanical Performance of Printed Circuit Heat Exchanger (PCHE)

Witiwat Jiragoontansiri, Teerapat Woravisuttsarakul, Rinrada Sae-Pueng, Yanin Sukjai

ASME J of Nuclear Rad Sci. April 2023, 9(2): 021401.

Paper No: NERS-21-1156

DOI: https://doi.org/10.1115/1.4054546

Published Online: June 15, 2022

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Topics: Airfoils, Flow (Dynamics), Geometry, Stress, Heat exchangers, Heat transfer, Temperature, Fluids, Structural analysis

Journal Articles

Neutronic and Thermal-Mechanical Coupling Schemes for Heat Pipe-Cooled Reactor Designs

Yugao Ma, Minyun Liu, Biheng Xie, Wenbin Han, Xiaoming Chai, Shanfang Huang, Hongxing Yu

ASME J of Nuclear Rad Sci. April 2022, 8(2): 021303.

Paper No: NERS-20-1207

DOI: https://doi.org/10.1115/1.4051612

Published Online: October 19, 2021

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Topics: Design, Displacement, Fuels, Geometry, Heat, Heat pipes, Molten salt reactors, Nuclear fission, Pipes, Temperature

Journal Articles

Superphénix Benchmark Part I: Results of Static Neutronics

Alexander Ponomarev, Konstantin Mikityuk, Liang Zhang, Evgeny Nikitin, Emil Fridman, Francisco Álvarez-Velarde, Pablo Romojaro Otero, Antonio Jiménez-Carrascosa, Nuria García-Herranz, Ben Lindley, Una Baker, Armin Seubert, Romain Henry

ASME J of Nuclear Rad Sci. January 2022, 8(1): 011320.

Paper No: NERS-21-1046

DOI: https://doi.org/10.1115/1.4051449

Published Online: October 8, 2021

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Topics: Density, Fuels, Rods, Sodium, Temperature, Steel, Geometry, Cladding systems (Building), Neutrons, Chemical kinetics

Journal Articles

Simulation Studies of the Sodium Hydraulic Behavior to Design a Mockup for Eddy Current Flowmeter Testing

Hubert Delacroix, Frédéric Navacchia

ASME J of Nuclear Rad Sci. January 2022, 8(1): 011317.

Paper No: NERS-20-1066

DOI: https://doi.org/10.1115/1.4052376

Published Online: October 4, 2021

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Topics: Evacuations, Flow (Dynamics), Flowmeters, Jets, Pipes, Sodium, Eddies (Fluid dynamics), Eddy currents (Electricity), Geometry, Design

Journal Articles

Coupled Neutronics–Mechanics Analysis Method for Evaluation of Reactivity Change Due to Core Distortion in Sodium Fast Reactor

Janos Bodi, Alexander Ponomarev, Konstantin Mikityuk

ASME J of Nuclear Rad Sci. January 2022, 8(1): 011307.

Paper No: NERS-20-1183

DOI: https://doi.org/10.1115/1.4050417

Published Online: August 3, 2021

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Topics: Deformation, Displacement, Finite element analysis, Geometry, Manufacturing, Sodium fast reactors, Fuels, Simulation, Absorption

Journal Articles

Pressurized Water Reactor Mixed Oxide/UO 2 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.

Paper No: NERS-20-1064

DOI: https://doi.org/10.1115/1.4048764

Published Online: March 16, 2021

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

Journal Articles

Improved Computational Fluid Dynamics Framework for Reactor Core Baffle Swelling Assessment

Yuliia Filonova, Yaroslav Dubyk, Vladislav Filonov, Vadym Kondratjuk

ASME J of Nuclear Rad Sci. January 2021, 7(1): 011404.

Paper No: NERS-20-1009

DOI: https://doi.org/10.1115/1.4047495

Published Online: October 5, 2020

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Topics: Boundary-value problems, Computational fluid dynamics, Coolants, Flow (Dynamics), Geometry, Temperature, Cooling, Temperature distribution, Metals

Journal Articles

Unequivocally Nonconservative Results From One Method of Imperfection Quantification in RCC-MR

Ashok Kumar, Anindya Chatterjee

ASME J of Nuclear Rad Sci. January 2021, 7(1): 011801.

Paper No: NERS-20-1001

DOI: https://doi.org/10.1115/1.4047494

Published Online: October 5, 2020

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Topics: Buckling, Shells, Stress, Geometry

Journal Articles

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.

Paper No: NERS-19-1168

DOI: https://doi.org/10.1115/1.4047441

Published Online: September 4, 2020

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

Journal Articles

Further Details of a Numerical Analysis on the Thermal Hydraulic Effect of Wrapped Wire Spacers in Fuel Bundle

Attila Kiss, Bence Mervay

ASME J of Nuclear Rad Sci. July 2020, 6(3): 031107.

Paper No: NERS-19-1069

DOI: https://doi.org/10.1115/1.4046842

Published Online: June 5, 2020

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Topics: Flow (Dynamics), Fuel rods, Geometry, Wire, Wall temperature, Fuels, Corners (Structural elements), Temperature

Journal Articles

Method Based on Characteristic Ray Information for Arbitrary Geometry Volume Calculation in NECP-X

Xinyu Zhou, Zhouyu Liu, Lu Cao, Liangzhi Cao, Hongchun Wu, Yu Han, Chuntao Tang

ASME J of Nuclear Rad Sci. April 2020, 6(2): 021901.

Paper No: NERS-19-1024

DOI: https://doi.org/10.1115/1.4045035

Published Online: February 24, 2020

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Topics: Errors, Geometry, Interpolation, Polynomials, Octrees, Sampling methods, Virtual reality

Journal Articles

Numerical Simulation of Siphon Breaker Systems for Open-Type Research Reactors

Damian E. Ramajo, Santiago F. Corzo, Norberto M. Nigro

ASME J of Nuclear Rad Sci. April 2020, 6(2): 021202.

Paper No: NERS-19-1039

DOI: https://doi.org/10.1115/1.4045121

Published Online: February 24, 2020

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Topics: Flow (Dynamics), Fluids, Pipes, Pressure, Simulation, Water, Computational fluid dynamics, Geometry, Drainage, Computer simulation

Journal Articles

A New Global Variance Reduction Technique Based on Geometry and Energy Splitting/Roulette

Z. Zheng, R. Li, Y. Zhou, Q. Mei, L. Deng

ASME J of Nuclear Rad Sci. January 2020, 6(1): 011102.

Paper No: NERS-18-1130

DOI: https://doi.org/10.1115/1.4045030

Published Online: November 8, 2019

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Topics: Computers, Errors, Fluence (Radiation measurement), Geometry, Neutrons, Particulate matter, Phase space, Photons, Weight (Mass), Dosimeters

Journal Articles

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.

Paper No: NERS-18-1123

DOI: https://doi.org/10.1115/1.4043100

Published Online: July 19, 2019

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

Journal Articles

Thermo-Mechanical Safety Analyses of Preliminary Design Experiments for 238 Pu Production

Christopher J. Hurt, James D. Freels, Prashant K. Jain, G. Ivan Maldonado

ASME J of Nuclear Rad Sci. January 2019, 5(1): 011002.

Paper No: NERS-16-1069

DOI: https://doi.org/10.1115/1.4041269

Published Online: January 24, 2019

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Topics: Heat, Irradiation (Radiation exposure), Safety, Temperature, Manufacturing, Heat transfer, Design, Shrinkage (Materials), Geometry, Cycles

Journal Articles

Obstructed View Factor Calculations for Multiple Obstructions in Closed Cavities

Fiaz Mahmood, Huasi Hu

ASME J of Nuclear Rad Sci. January 2019, 5(1): 011012.

Paper No: NERS-17-1218

DOI: https://doi.org/10.1115/1.4041563

Published Online: January 24, 2019

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Topics: Cavities, Geometry, Pellet fusion, Radiation (Physics), Shades and shadows, String, Computer software, FORTRAN

Journal Articles

Nozzle Geometry Effect on Stratified Layer Erosion by Vertical Turbulent Jet

L. Ishay, U. Bieder, G. Ziskind, A. Rashkovan

ASME J of Nuclear Rad Sci. July 2017, 3(3): 030902.

Paper No: NERS-16-1105

DOI: https://doi.org/10.1115/1.4035693

Published Online: May 25, 2017

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Topics: Geometry, Nozzles, Turbulence, Flow (Dynamics), Jets, Erosion, Buoyancy

Journal Articles

The Powerful Method of Characteristics Module in Advanced Neutronics Lattice Code KYLIN-2

Xiaoming Chai, Xiaolan Tu, Wei Lu, Zongjian Lu, Dong Yao, Qing Li, Wenbin Wu

ASME J of Nuclear Rad Sci. July 2017, 3(3): 031004.

Paper No: NERS-16-1110

DOI: https://doi.org/10.1115/1.4035934

Published Online: May 25, 2017

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Topics: Boundary-value problems, Reflection, Trajectories (Physics), Geometry, Rotation

Journal Articles

Influence of Boundary Conditions, Vessel Geometry, and Simulant Materials on the Heat Transfer of Volumetrically Heated Melt in a Light Water Reactor Lower Head

X. Gaus-Liu, A. Miassoedov

ASME J of Nuclear Rad Sci. July 2017, 3(3): 031003.

Paper No: NERS-16-1107

DOI: https://doi.org/10.1115/1.4035853

Published Online: May 25, 2017

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Topics: Boundary-value problems, Cooling, Heat flux, Heat transfer, Temperature, Vessels, Geometry, Insulation, Water

Journal Articles

Bypass Flow Resistance in Prismatic Gas-Cooled Nuclear Reactors

Donald M. McEligot, Richard W. Johnson

ASME J of Nuclear Rad Sci. January 2017, 3(1): 011003.

Paper No: NERS-16-1046

DOI: https://doi.org/10.1115/1.4035047

Published Online: December 20, 2016

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Topics: Flow (Dynamics), Friction, Turbulence, Computational fluid dynamics, Laminar flow, Ducts, Reynolds number, Geometry

Journal citation

NARROW

The Effect of Flow Channel Geometry on Thermomechanical Performance of Printed Circuit Heat Exchanger (PCHE)

Neutronic and Thermal-Mechanical Coupling Schemes for Heat Pipe-Cooled Reactor Designs

Superphénix Benchmark Part I: Results of Static Neutronics

Simulation Studies of the Sodium Hydraulic Behavior to Design a Mockup for Eddy Current Flowmeter Testing

Coupled Neutronics–Mechanics Analysis Method for Evaluation of Reactivity Change Due to Core Distortion in Sodium Fast Reactor

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

Improved Computational Fluid Dynamics Framework for Reactor Core Baffle Swelling Assessment

Unequivocally Nonconservative Results From One Method of Imperfection Quantification in RCC-MR

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

Further Details of a Numerical Analysis on the Thermal Hydraulic Effect of Wrapped Wire Spacers in Fuel Bundle

Method Based on Characteristic Ray Information for Arbitrary Geometry Volume Calculation in NECP-X

Numerical Simulation of Siphon Breaker Systems for Open-Type Research Reactors

A New Global Variance Reduction Technique Based on Geometry and Energy Splitting/Roulette

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

Thermo-Mechanical Safety Analyses of Preliminary Design Experiments for 238 Pu Production

Obstructed View Factor Calculations for Multiple Obstructions in Closed Cavities

Nozzle Geometry Effect on Stratified Layer Erosion by Vertical Turbulent Jet

The Powerful Method of Characteristics Module in Advanced Neutronics Lattice Code KYLIN-2

Influence of Boundary Conditions, Vessel Geometry, and Simulant Materials on the Heat Transfer of Volumetrically Heated Melt in a Light Water Reactor Lower Head

Bypass Flow Resistance in Prismatic Gas-Cooled Nuclear Reactors

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