Volume 4 Issue 3 | ASME J. of Nuclear Rad Sci.

Special Section Papers

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

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

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

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

Abstract

View articletitled, 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

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

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

Abstract

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

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

Setup of the Supercritical CO₂ 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. doi: https://doi.org/10.1115/1.4039595

Abstract

View articletitled, Setup of the Supercritical CO2 Test Facility “SCARLETT” for Basic Experimental Investigations of a Compact Heat Exchanger for an Innovative Decay Heat Removal System

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

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

Abstract

View articletitled, Irradiation Issues and Material Selection for Canadian SCWR Components

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

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

Abstract

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

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

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

Abstract

View articletitled, Multiphysics Modeling of Pressurized Water Reactor Fuel Performance

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

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

Abstract

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

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

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

Abstract

View articletitled, Parallel Analysis of Linear Systems in CORTH and KYLIN2

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

Mechanical Properties of Cubic (U,Zr)O₂

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

Abstract

View articletitled, Mechanical Properties of Cubic (U,Zr)O2

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

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

Abstract

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

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

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

Abstract

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

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

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

Abstract

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

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

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

Abstract

View articletitled, Investigations of Rod Positions for Treat M8CAL Analyses

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

Abstract

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

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

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

Abstract

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

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Topics: Corrosion , Oxygen , Stainless steel , Steel

Study on Radial Temperature Distribution of Aluminum Dispersed Nuclear Fuels: U₃O₈-Al, U₃Si₂-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. doi: https://doi.org/10.1115/1.4039886

Abstract

View articletitled, Study on Radial Temperature Distribution of Aluminum Dispersed Nuclear Fuels: U3O8-Al, U3Si2-Al, and UN-Al

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

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

Abstract

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

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

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

Abstract

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

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Special Section Papers

Precautions at Fukushima That Would Have Suppressed the Accident Severity

Kenji Iino, Ritsuo Yoshioka, Masao Fuchigami, Masayuki Nakao

ASME J of Nuclear Rad Sci. July 2018, 4(3): 031007. doi: https://doi.org/10.1115/1.4039343

Abstract

View articletitled, Precautions at Fukushima That Would Have Suppressed the Accident Severity

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Topics: Accidents , Earthquakes , Fukushima nuclear disaster, Japan, 2011 , Seawater , Tsunamis , Water , Heat , Pumps , Electricity (Physics) , Evaporation

Uncertainty Analysis for Source Term Evaluation of High Temperature Gas-Cooled Reactor Under Accident Conditions—Identification of Influencing Factors in Loss-of-Forced Circulation Accidents

Yuki Honda, Hiroyuki Sato, Shigeaki Nakagawa, Hirofumi Ohashi

ASME J of Nuclear Rad Sci. July 2018, 4(3): 031013. doi: https://doi.org/10.1115/1.4039066

Abstract

View articletitled, Uncertainty Analysis for Source Term Evaluation of High Temperature Gas-Cooled Reactor Under Accident Conditions—Identification of Influencing Factors in Loss-of-Forced Circulation Accidents

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Topics: Accidents , Fuels , Temperature , Uncertainty , Uncertainty analysis , Very high temperature reactors , Heat , Failure

A Numerical Analysis Method of Impurity Precipitation on Mesh Wire of Cold Trap in Fast Breeder Reactor

Akinori Tamura, Shiro Takahashi, Hiroyuki Nakata, Akio Takota

ASME J of Nuclear Rad Sci. July 2018, 4(3): 031015. doi: https://doi.org/10.1115/1.4039037

Abstract

View articletitled, A Numerical Analysis Method of Impurity Precipitation on Mesh Wire of Cold Trap in Fast Breeder Reactor

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Topics: Flow (Dynamics) , Numerical analysis , Precipitation , Reynolds number , Simulation , Wire , Breeder reactors , Computer simulation , Pressure , Sodium

Technical Brief

Analysis of the Effect of Beam Divergence Angle on Back-Streaming Electron Region in Ion Source for EAST-Neutral Beam Injection

Hu Chundong, Wu Mingshan, Xie Yahong, Wei Jianglong, Yu Ling

ASME J of Nuclear Rad Sci. July 2018, 4(3): 034501. doi: https://doi.org/10.1115/1.4039694

Abstract

View articletitled, Analysis of the Effect of Beam Divergence Angle on Back-Streaming Electron Region in Ion Source for EAST-Neutral Beam Injection

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Topics: Electrons , Ions , Silencers , Heat

Research Progress of Red Oil Explosion Accidents in Nuclear Fuel Reprocessing Plant

Chunlong Zhang, Hui He, Shangui Zhao, Shijun Wang, XinHua Liu

ASME J of Nuclear Rad Sci. July 2018, 4(3): 034502. doi: https://doi.org/10.1115/1.4039599

Abstract

View articletitled, Research Progress of Red Oil Explosion Accidents in Nuclear Fuel Reprocessing Plant

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A Density Functional Theory Study on the Diffusion of Fission Gas Atoms in Uranium Dioxide

Qiang Zhao, Zheng Zhang, Xiaoping Ouyang

ASME J of Nuclear Rad Sci. July 2018, 4(3): 034503. doi: https://doi.org/10.1115/1.4039885

Abstract

View articletitled, A Density Functional Theory Study on the Diffusion of Fission Gas Atoms in Uranium Dioxide

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Topics: Atoms , Density functional theory , Diffusion (Physics) , Nuclear fission , Uranium , Elasticity , Fuels , Oxygen

Special Section Papers

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

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

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

Setup of the Supercritical CO₂ Test Facility “SCARLETT” for Basic Experimental Investigations of a Compact Heat Exchanger for an Innovative Decay Heat Removal System

Irradiation Issues and Material Selection for Canadian SCWR Components

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

Multiphysics Modeling of Pressurized Water Reactor Fuel Performance

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

Parallel Analysis of Linear Systems in CORTH and KYLIN2

Mechanical Properties of Cubic (U,Zr)O₂

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

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

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

Investigations of Rod Positions for Treat M8CAL Analyses

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

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

Study on Radial Temperature Distribution of Aluminum Dispersed Nuclear Fuels: U₃O₈-Al, U₃Si₂-Al, and UN-Al

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

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

Special Section Papers

Precautions at Fukushima That Would Have Suppressed the Accident Severity

Uncertainty Analysis for Source Term Evaluation of High Temperature Gas-Cooled Reactor Under Accident Conditions—Identification of Influencing Factors in Loss-of-Forced Circulation Accidents

A Numerical Analysis Method of Impurity Precipitation on Mesh Wire of Cold Trap in Fast Breeder Reactor

Technical Brief

Analysis of the Effect of Beam Divergence Angle on Back-Streaming Electron Region in Ion Source for EAST-Neutral Beam Injection

Research Progress of Red Oil Explosion Accidents in Nuclear Fuel Reprocessing Plant

A Density Functional Theory Study on the Diffusion of Fission Gas Atoms in Uranium Dioxide

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