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    Journal of Nuclear Engineering and Radiation Science

    EISSN: 2332-8975
    ISSN: 2332-8983
    Priority: 4
    Publisher: American Society of Mechanical Engineers
    Description: The Journal of Nuclear Engineering and Radiation Science is ASME’s latest title within the energy sector. The publication is for specialists in the nuclear/power engineering areas of industry, academia, and government More ...

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    Professor Geoffrey Hewitt on His 80th Birthday 

    Source: Journal of Nuclear Engineering and Radiation Science:;2015:;volume( 001 ):;issue: 001:;page 10301
    Author(s): Awad, M. M.; Mayinger, F.; Lahey, Jr. ,R. T.
    Publisher: The American Society of Mechanical Engineers (ASME)
    Abstract: Professor Geoffrey Hewitt is one of the wellknown names in the field of heat transfer, twophase flow, and nuclear engineering and is well respected among his colleagues in the heattransfer and nuclearengineering community ...
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    Nuclear Power as a Basis for Future Electricity Generation 

    Source: Journal of Nuclear Engineering and Radiation Science:;2015:;volume( 001 ):;issue: 001:;page 11001
    Author(s): Pioro, I.; Duffey, R.
    Publisher: The American Society of Mechanical Engineers (ASME)
    Abstract: It is well known that electrical power generation is the key factor for advances in industry, agriculture, technology, and standards of living. Also, a strong power industry with diverse energy sources is very important ...
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    Numerical Simulation of Temperature Distribution in a Containment Vessel of an Operating PWR Plant 

    Source: Journal of Nuclear Engineering and Radiation Science:;2015:;volume( 001 ):;issue: 001:;page 11002
    Author(s): Utanohara, Yoichi; Murase, Michio; Masui, Akihiro; Inomata, Ryo; Kamiya, Yuji
    Publisher: The American Society of Mechanical Engineers (ASME)
    Abstract: The structural integrity of the containment vessel (CV) for a pressurized water reactor (PWR) plant under a lossofcoolant accident is evaluated by a safety analysis code that uses the average temperature of gas phase in ...
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    Computational Fluid Dynamics Analysis for Asymmetric Power Generation in a Prismatic Fuel Block of Fluoride Salt Cooled High Temperature Test Reactor 

    Source: Journal of Nuclear Engineering and Radiation Science:;2015:;volume( 001 ):;issue: 001:;page 11003
    Author(s): Cheng, Wen; Sun, Kaichao; Hu, Lin; Chieng, Ching
    Publisher: The American Society of Mechanical Engineers (ASME)
    Abstract: The fluoridesaltcooled hightemperature reactor (FHR) is an advanced reactor concept that uses tristructural isotropic (TRISO) hightemperature fuel and lowpressure liquid salt coolant. A 20MWth test reactor, as the key step ...
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    Application of the System Based Code Concept to the Determination of In Service Inspection Requirements 

    Source: Journal of Nuclear Engineering and Radiation Science:;2015:;volume( 001 ):;issue: 001:;page 11004
    Author(s): Takaya, Shigeru; Asayama, Tai; Kamishima, Yoshio; Machida, Hideo; Watanabe, Daigo; Nakai, Satoru; Morishita, Masaki
    Publisher: The American Society of Mechanical Engineers (ASME)
    Abstract: A new process for determination of inservice inspection (ISI) requirements was proposed on the basis of the system based code concept to realize effective and rational ISI by properly taking into account plantspecific ...
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    Study on Neutronics and Thermalhydraulics Characteristics of 1200 MWel Pressure Channel Supercritical Water Cooled Reactor 

    Source: Journal of Nuclear Engineering and Radiation Science:;2015:;volume( 001 ):;issue: 001:;page 11006
    Author(s): Miletic, Marija; Peiman, Wargha; Farah, Amjad; Samuel, Jeffrey; Dragunov, Alexey; Pioro, Igor
    Publisher: The American Society of Mechanical Engineers (ASME)
    Abstract: Nuclear power becomes more and more important in many countries worldwide as a basis for current and future electrical energy generation. The largest group of operating nuclear power plants (NPPs) equipped with watercooled ...
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    Experimental Modeling of Wind Driven Bin by Bin Resuspension Factors of Freshly Fallen Radionuclides After an Energetic Release From a Radiological Dispersal Device 

    Source: Journal of Nuclear Engineering and Radiation Science:;2015:;volume( 001 ):;issue: 001:;page 11005
    Author(s): Perera, Sharman; Waller, Edward; Akhtar, Ali
    Publisher: The American Society of Mechanical Engineers (ASME)
    Abstract: Smallscale experiments were carried out to characterize the resuspension factor of radioactive lanthanum oxide powder in an environmentally controlled wind tunnel, with the majority using particle sizes less than 10 خ¼m ...
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    Development of a Thermal Hydraulic Analysis Code and Transient Analysis for a Fluoride Salt Cooled High Temperature Test Reactor 

    Source: Journal of Nuclear Engineering and Radiation Science:;2015:;volume( 001 ):;issue: 001:;page 11007
    Author(s): Xiao, Yao; Hu, Lin; Qiu, Suizheng; Zhang, Dalin; Guanghui, Su; Tian, Wenxi
    Publisher: The American Society of Mechanical Engineers (ASME)
    Abstract: The fluoridesaltcooled hightemperature reactor (FHR) is an advanced reactor concept that uses hightemperature tristructural isotropic (TRISO) fuel with a lowpressure liquid salt coolant. Design of the fluoridesaltcooled ...
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    Parametric Lattice Study of a Graphite Moderated Molten Salt Reactor 

    Source: Journal of Nuclear Engineering and Radiation Science:;2015:;volume( 001 ):;issue: 001:;page 11009
    Author(s): Hombourger, Boris A.; K™epel, Ji™أ­; Mikityuk, Konstantin; Pautz, Andreas
    Publisher: The American Society of Mechanical Engineers (ASME)
    Abstract: Molten salt reactors (MSRs) are promising advanced nuclear reactors for closure of the fuel cycle. This paper discusses the core design of graphitemoderated MSRs, thanks to a parametric study of the fuel and moderator ...
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    Enhancing Numerical Stability of a Two Fluid Model by the Use of Interfacial Pressure Terms 

    Source: Journal of Nuclear Engineering and Radiation Science:;2015:;volume( 001 ):;issue: 002:;page 21001
    Author(s): Okawa, Tomio
    Publisher: The American Society of Mechanical Engineers (ASME)
    Abstract: Analytical and numerical investigations were carried out to show that the characteristics and the numerical stability of the twofluid model are improved by the use of the interfacial pressure terms that express the pressure ...
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