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Journal Articles

Investigations of Rod Positions for Treat M8CAL Analyses

Zachary Weems, Sedat Goluoglu, Mark D. DeHart

ASME J of Nuclear Rad Sci. July 2018, 4(3): 031017.

Paper No: NERS-17-1071

DOI: https://doi.org/10.1115/1.4038929

Published Online: May 16, 2018

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Journal Articles

Correlation of Interfacial Friction Coefficients for Predicting Countercurrent Flow Limitation at a Sharp-Edged Lower End of Vertical Pipes

Michio Murase, Takayoshi Kusunoki, Koji Nishida, Raito Goda, Akio Tomiyama

ASME J of Nuclear Rad Sci. July 2018, 4(3): 031001.

Paper No: NERS-17-1057

DOI: https://doi.org/10.1115/1.4039438

Published Online: May 16, 2018

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Topics: Computation, Flow (Dynamics), Pipes, Water, Friction, Steam, High pressure (Physics)

Journal Articles

Effect of Lead-Bismuth Eutectic Oxygen Concentration on the Onset of Dissolution Corrosion in 316 L Austenitic Stainless Steel at 450 °C

Oksana Klok, Konstantina Lambrinou, Serguei Gavrilov, Jun Lim, Iris De Graeve

ASME J of Nuclear Rad Sci. July 2018, 4(3): 031019.

Paper No: NERS-17-1269

DOI: https://doi.org/10.1115/1.4039598

Published Online: May 16, 2018

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Topics: Corrosion, Oxygen, Stainless steel, Steel

Journal Articles

Mechanical Properties of Cubic (U,Zr)O 2

Toru Kitagaki, Takanori Hoshino, Kimihiko Yano, Nobuo Okamura, Hiroshi Ohara, Tetsuo Fukasawa, Kenji Koizumi

ASME J of Nuclear Rad Sci. July 2018, 4(3): 031011.

Paper No: NERS-17-1069

DOI: https://doi.org/10.1115/1.4039847

Published Online: May 16, 2018

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Topics: Elastic moduli, Fracture toughness, Mechanical properties, Vickers hardness testing, Zirconium, Fracture (Materials), Fuels, Solid solutions

Journal Articles

Hydrogen–Air–Steam Deflagration Experiment Simulated Using Different Turbulent Flame-Speed Closure Models

Holler Tadej, Ed M. J. Komen, Kljenak Ivo

ASME J of Nuclear Rad Sci. July 2018, 4(3): 031009.

Paper No: NERS-16-1126

DOI: https://doi.org/10.1115/1.4039067

Published Online: May 16, 2018

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Topics: Combustion, Explosions, Flames, Hydrogen, Turbulence, Pressure, Computational fluid dynamics, Simulation, Boundary-value problems

Journal Articles

Irradiation Issues and Material Selection for Canadian SCWR Components

L. Walters, M. Wright, D. Guzonas

ASME J of Nuclear Rad Sci. July 2018, 4(3): 031005.

Paper No: NERS-17-1045

DOI: https://doi.org/10.1115/1.4038367

Published Online: May 16, 2018

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Topics: Alloys, Irradiation (Radiation exposure), Supercritical water reactors, Temperature, Neutrons, Fuels, Water, Stainless steel, Helium

Journal Articles

Study on Radial Temperature Distribution of Aluminum Dispersed Nuclear Fuels: U 3 O 8 -Al, U 3 Si 2 -Al, and UN-Al

Jayangani I. Ranasinghe, Ericmoore Jossou, Linu Malakkal, Barbara Szpunar, Jerzy A. Szpunar

ASME J of Nuclear Rad Sci. July 2018, 4(3): 031020.

Paper No: NERS-17-1304

DOI: https://doi.org/10.1115/1.4039886

Published Online: May 16, 2018

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Topics: Fuels, Nuclear fuels, Thermal conductivity, Temperature, Temperature gradient, Temperature profiles

Journal Articles

Verifying Calculation of the Parameters of AP1000 Core Design Based on MCNP Model

Xiong Wenbin, Cao Jian, Huang Chaoyun, Bie Yewang, Wang Yanqi, Li Jufeng

ASME J of Nuclear Rad Sci. July 2018, 4(3): 031018.

Paper No: NERS-17-1132

DOI: https://doi.org/10.1115/1.4039596

Published Online: May 16, 2018

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Topics: Design, Fuels, Rods, Manufacturing, Nuclear power stations, Modeling, Boron, Physics

Journal Articles

Numerical Investigation of Convective Heat Transfer to Supercritical Pressure Hydrogen in a Straight Tube

Yu Ji, Jun Sun, Lei Shi

ASME J of Nuclear Rad Sci. July 2018, 4(3): 031012.

Paper No: NERS-17-1193

DOI: https://doi.org/10.1115/1.4039600

Published Online: May 16, 2018

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Topics: Convection, Heat transfer, Hydrogen, Pressure, Simulation, Turbulence, Flow (Dynamics), Density, Temperature, Viscosity

Journal Articles

Parallel Analysis of Linear Systems in CORTH and KYLIN2

Pingzhou Ming, Dingyong Chen, Bin Wu, Wei Lu, Dong Liu, Hongxing Yu

ASME J of Nuclear Rad Sci. July 2018, 4(3): 031010.

Paper No: NERS-17-1143

DOI: https://doi.org/10.1115/1.4039036

Published Online: May 16, 2018

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Topics: Linear systems, Thermal hydraulics, Manufacturing, Cores (Molding materials)

Journal Articles

Experimental Study on Melt Coolability Capability of Calandria Vault Water During Severe Accident in Indian PHWRs for Prolonged Duration

Sumit V. Prasad, A. K. Nayak

ASME J of Nuclear Rad Sci. July 2018, 4(3): 031014.

Paper No: NERS-17-1062

DOI: https://doi.org/10.1115/1.4039636

Published Online: May 16, 2018

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Topics: Accidents, Boiling, Heat transfer, Heat transfer coefficients, Heavy water reactors, Temperature, Vessels, Water, Heat, Natural convection

Journal Articles

Insight From Recent Experimental and Empirical-Model Studies on Flow-Regime Characteristics in Debris Bed Formation Behavior

Songbai Cheng, Ting Zhang, Jinjiang Cui, Pengfeng Gong, Yujia Qian

ASME J of Nuclear Rad Sci. July 2018, 4(3): 031003.

Paper No: NERS-17-1197

DOI: https://doi.org/10.1115/1.4039597

Published Online: May 16, 2018

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Topics: Particulate matter, Pipes, Shapes, Water, Convection

Journal Articles

Method and Validation for Measurement of Effective Thermal Diffusivity and Conductivity of Pebble Bed in High Temperature Gas-Cooled Reactors

Yongyong Wu, Cheng Ren, Rui Li, Xingtuan Yang, Jiyuan Tu, Shengyao Jiang

ASME J of Nuclear Rad Sci. July 2018, 4(3): 031006.

Paper No: NERS-17-1109

DOI: https://doi.org/10.1115/1.4039035

Published Online: May 16, 2018

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Topics: Errors, Temperature, Thermal conductivity, Thermal diffusivity, Very high temperature reactors, Low temperature, Safety, Heat conduction, Algorithms, Electrical conductivity

Journal Articles

Characteristics of Thermal–Hydraulic and Heat Transfer in Liquid Windowless Target of Accelerator Driven Subcritical

Feng Wang, Qiang Wen, Xue Qin

ASME J of Nuclear Rad Sci. July 2018, 4(3): 031021.

Paper No: NERS-17-1098

DOI: https://doi.org/10.1115/1.4039034

Published Online: May 16, 2018

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Topics: Alloys, Flow (Dynamics), Fluids, Heat transfer, Pressure, Cavitation, Computational fluid dynamics, Spallation (Nuclear physics), Coolants, Vapors

Journal Articles

Analysis of Inertization Strategies for the Filtered Containment Venting System in Cofrentes Nuclear Power Plant

Kevin Fernández-Cosials, Gonzalo Jiménez, César Serrano, Luisa Ibáñez, Ángel Peinado

ASME J of Nuclear Rad Sci. July 2018, 4(3): 031016.

Paper No: NERS-17-1065

DOI: https://doi.org/10.1115/1.4038595

Published Online: May 16, 2018

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Topics: Containment, Hydrogen, Nitrogen, Nuclear power stations, Oxygen, Risk, Combustion, Simulation

Journal Articles

Multiphysics Modeling of Pressurized Water Reactor Fuel Performance

Wang Zhu, Zhang Chungyu, Yuan Cenxi

ASME J of Nuclear Rad Sci. July 2018, 4(3): 031008.

Paper No: NERS-17-1103

DOI: https://doi.org/10.1115/1.4039848

Published Online: May 16, 2018

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Topics: Cladding systems (Building), Fuel rods, Fuels, Modeling, Nuclear fission, Temperature, Pressurized water reactors, Stress, Accidents

Journal Articles

Setup of the Supercritical CO 2 Test Facility “SCARLETT” for Basic Experimental Investigations of a Compact Heat Exchanger for an Innovative Decay Heat Removal System

Wolfgang Flaig, Rainer Mertz, Joerg Starflinger

ASME J of Nuclear Rad Sci. July 2018, 4(3): 031004.

Paper No: NERS-17-1121

DOI: https://doi.org/10.1115/1.4039595

Published Online: May 16, 2018

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Topics: Carbon dioxide, Compressors, Design, Flow (Dynamics), Heat, Heat exchangers, Pressure, Supercritical carbon dioxide, Temperature, Test facilities

Journal Articles

Crack Growth and Tolerance of Stainless Steel Canisters in the Marine Environment

Chang Heui-Yung

ASME J of Nuclear Rad Sci. July 2018, 4(3): 031022.

Paper No: NERS-17-1209

DOI: https://doi.org/10.1115/1.4039501

Published Online: May 16, 2018

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Journal Articles

Numerical Investigations of the Effect of Radial Power Distribution and Inlet Orifice on the Stability Behavior of Parallel Multichannel Type Natural Circulation Boiling Water Reactor

Sapna Singh, Garima Singal, A. K. Nayak, Umasankari Kannan

ASME J of Nuclear Rad Sci. July 2018, 4(3): 031002.

Paper No: NERS-17-1075

DOI: https://doi.org/10.1115/1.4039594

Published Online: May 16, 2018

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Topics: Flow (Dynamics), Oscillations, Stability, Boiling water reactors

Journal Articles

Handling and Conditioning Techniques of Activated Swarfs for the Decommissioning of the E. Fermi Nuclear Power Plant

Massimo Di Pietro, Sergio Pistelli, Eugenio Garneri, Rosa Lo Frano, Riccardo Ciolini

ASME J of Nuclear Rad Sci. April 2018, 4(2): 020910.

Paper No: NERS-16-1125

DOI: https://doi.org/10.1115/1.4038556

Published Online: March 5, 2018

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Topics: Circuits, Ejectors, Flow (Dynamics), Nuclear decommissioning, Nuclear power stations, Scrap metals, Suction, Water, Heat shielding

2 3 4

Journal citation

NARROW

Investigations of Rod Positions for Treat M8CAL Analyses

Correlation of Interfacial Friction Coefficients for Predicting Countercurrent Flow Limitation at a Sharp-Edged Lower End of Vertical Pipes

Effect of Lead-Bismuth Eutectic Oxygen Concentration on the Onset of Dissolution Corrosion in 316 L Austenitic Stainless Steel at 450 °C

Mechanical Properties of Cubic (U,Zr)O 2

Hydrogen–Air–Steam Deflagration Experiment Simulated Using Different Turbulent Flame-Speed Closure Models

Irradiation Issues and Material Selection for Canadian SCWR Components

Study on Radial Temperature Distribution of Aluminum Dispersed Nuclear Fuels: U 3 O 8 -Al, U 3 Si 2 -Al, and UN-Al

Verifying Calculation of the Parameters of AP1000 Core Design Based on MCNP Model

Numerical Investigation of Convective Heat Transfer to Supercritical Pressure Hydrogen in a Straight Tube

Parallel Analysis of Linear Systems in CORTH and KYLIN2

Experimental Study on Melt Coolability Capability of Calandria Vault Water During Severe Accident in Indian PHWRs for Prolonged Duration

Insight From Recent Experimental and Empirical-Model Studies on Flow-Regime Characteristics in Debris Bed Formation Behavior

Method and Validation for Measurement of Effective Thermal Diffusivity and Conductivity of Pebble Bed in High Temperature Gas-Cooled Reactors

Characteristics of Thermal–Hydraulic and Heat Transfer in Liquid Windowless Target of Accelerator Driven Subcritical

Analysis of Inertization Strategies for the Filtered Containment Venting System in Cofrentes Nuclear Power Plant

Multiphysics Modeling of Pressurized Water Reactor Fuel Performance

Setup of the Supercritical CO 2 Test Facility “SCARLETT” for Basic Experimental Investigations of a Compact Heat Exchanger for an Innovative Decay Heat Removal System

Crack Growth and Tolerance of Stainless Steel Canisters in the Marine Environment

Numerical Investigations of the Effect of Radial Power Distribution and Inlet Orifice on the Stability Behavior of Parallel Multichannel Type Natural Circulation Boiling Water Reactor

Handling and Conditioning Techniques of Activated Swarfs for the Decommissioning of the E. Fermi Nuclear Power Plant

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