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Volume 1, Issue 1

January 2015

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ISSN 2332-8983

EISSN 2332-8975

In this Issue

Editorial
Guest Editorial
Research Papers
Technical Brief

Editorial

Igor L. Pioro

ASME J of Nuclear Rad Sci. January 2015, 1(1): 010201. doi: https://doi.org/10.1115/1.4029141

Extract

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Topics: China , Design , Nuclear engineering , Nuclear fuel cycle , Nuclear power , Nuclear power stations , Nuclear reactors , Physics , Radiation (Physics) , Risk

NED Chair’s Message

Asif Arastu

ASME J of Nuclear Rad Sci. January 2015, 1(1): 010202. doi: https://doi.org/10.1115/1.4029140

Extract

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Topics: Nuclear engineering , Nuclear industry , Nuclear power , Radiation (Physics) , China , Climate change , Education , Electric power generation , Energy generation , Ethics

Guest Editorial

Professor Geoffrey Hewitt on His 80th Birthday

M. M. Awad, F. Mayinger, R. T. Lahey, Jr.

ASME J of Nuclear Rad Sci. January 2015, 1(1): 010301. doi: https://doi.org/10.1115/1.4029139

Extract

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Topics: Engineering teachers

Research Papers

Nuclear Power as a Basis for Future Electricity Generation

I. Pioro, R. Duffey

ASME J of Nuclear Rad Sci. January 2015, 1(1): 011001. doi: https://doi.org/10.1115/1.4029420

Abstract

View articletitled, Nuclear Power as a Basis for Future Electricity Generation

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Numerical Simulation of Temperature Distribution in a Containment Vessel of an Operating PWR Plant

Yoichi Utanohara, Michio Murase, Akihiro Masui, Ryo Inomata, Yuji Kamiya

ASME J of Nuclear Rad Sci. January 2015, 1(1): 011002. doi: https://doi.org/10.1115/1.4026389

Abstract

View articletitled, Numerical Simulation of Temperature Distribution in a Containment Vessel of an Operating PWR Plant

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Topics: Computer simulation , Flow (Dynamics) , Pressurized water reactors , Temperature , Temperature distribution , Containment vessels , Heat , Simulation

Computational Fluid Dynamics Analysis for Asymmetric Power Generation in a Prismatic Fuel Block of Fluoride-Salt-Cooled High-Temperature Test Reactor

Wen-Chi Cheng, Kaichao Sun, Lin-Wen Hu, Ching-Chang Chieng

ASME J of Nuclear Rad Sci. January 2015, 1(1): 011003. doi: https://doi.org/10.1115/1.4026391

Abstract

View articletitled, Computational Fluid Dynamics Analysis for Asymmetric Power Generation in a Prismatic Fuel Block of Fluoride-Salt-Cooled High-Temperature Test Reactor

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Topics: Computational fluid dynamics , Coolants , Energy generation , Fuels , Graphite , Heat flux , Laminar flow , Temperature , Turbulence , Wall temperature

Application of the System Based Code Concept to the Determination of In-Service Inspection Requirements

Shigeru Takaya, Tai Asayama, Yoshio Kamishima, Hideo Machida, Daigo Watanabe, Satoru Nakai, Masaki Morishita

ASME J of Nuclear Rad Sci. January 2015, 1(1): 011004. doi: https://doi.org/10.1115/1.4026392

Abstract

View articletitled, Application of the System Based Code Concept to the Determination of In-Service Inspection Requirements

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Topics: Creep , Design , Failure , Fatigue , Fracture (Materials) , In-service inspection , Probability , Reliability , Safety , Stress

Experimental Modeling of Wind-Driven Bin-by-Bin Resuspension Factors of Freshly Fallen Radionuclides After an Energetic Release From a Radiological Dispersal Device

Sharman Perera, Edward Waller, Ali Akhtar

ASME J of Nuclear Rad Sci. January 2015, 1(1): 011005. doi: https://doi.org/10.1115/1.4026390

Abstract

View articletitled, Experimental Modeling of Wind-Driven Bin-by-Bin Resuspension Factors of Freshly Fallen Radionuclides After an Energetic Release From a Radiological Dispersal Device

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Topics: Particle size , Particulate matter , Surface roughness , Wind tunnels , Plates (structures) , Wind , Radiological dispersal devices

Study on Neutronics and Thermalhydraulics Characteristics of 1200-MW_el Pressure-Channel Supercritical Water-Cooled Reactor

Marija Miletic, Wargha Peiman, Amjad Farah, Jeffrey Samuel, Alexey Dragunov, Igor Pioro

ASME J of Nuclear Rad Sci. January 2015, 1(1): 011006. doi: https://doi.org/10.1115/1.4026387

Abstract

View articletitled, Study on Neutronics and Thermalhydraulics Characteristics of 1200-MW<sub>el</sub> Pressure-Channel Supercritical Water-Cooled Reactor

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Topics: Computational fluid dynamics , Coolants , Fuels , Pressure , Supercritical water reactors , Temperature , Water , Heat transfer , Heat flux

Development of a Thermal-Hydraulic Analysis Code and Transient Analysis for a Fluoride-Salt-Cooled High-Temperature Test Reactor

Yao Xiao, Lin-Wen Hu, Suizheng Qiu, Dalin Zhang, Su Guanghui, Wenxi Tian

ASME J of Nuclear Rad Sci. January 2015, 1(1): 011007. doi: https://doi.org/10.1115/1.4026394

Abstract

View articletitled, Development of a Thermal-Hydraulic Analysis Code and Transient Analysis for a Fluoride-Salt-Cooled High-Temperature Test Reactor

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Topics: Accidents , Coolants , Design , Flow (Dynamics) , Fuels , High temperature , Temperature , Transient analysis , Transients (Dynamics) , Heat transfer