Journal of Nuclear Engineering and Radiation Science: Recent submissions
Now showing items 901-913 of 913
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Development of a Thermal Hydraulic Analysis Code and Transient Analysis for a Fluoride Salt Cooled High Temperature Test Reactor
(The American Society of Mechanical Engineers (ASME), 2015)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 ... -
Parametric Lattice Study of a Graphite Moderated Molten Salt Reactor
(The American Society of Mechanical Engineers (ASME), 2015)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 ... -
Study on Specifics of Forced Convective Heat Transfer in Supercritical Carbon Dioxide
(The American Society of Mechanical Engineers (ASME), 2015)The appropriate description of heat transfer to coolants at the supercritical state is limited by the current understanding. Thus, this poses one of the main challenges in the development of supercriticalfluids applications ... -
A Note on Mixture Density Using the Shannak Definition
(The American Society of Mechanical Engineers (ASME), 2015)In this study, a note on mixture density using the Shannak definition of the Froude number is presented (Shannak, B., 2009, “Dimensionless Numbers for TwoPhase and Multiphase Flow,†Proceedings of the International ... -
Application of the System Based Code Concept to the Determination of In Service Inspection Requirements
(The American Society of Mechanical Engineers (ASME), 2015)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 ... -
Experimental Modeling of Wind Driven Bin by Bin Resuspension Factors of Freshly Fallen Radionuclides After an Energetic Release From a Radiological Dispersal Device
(The American Society of Mechanical Engineers (ASME), 2015)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 ... -
Nuclear Power as a Basis for Future Electricity Generation
(The American Society of Mechanical Engineers (ASME), 2015)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 ... -
Numerical Simulation of Temperature Distribution in a Containment Vessel of an Operating PWR Plant
(The American Society of Mechanical Engineers (ASME), 2015)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 ... -
Computational Fluid Dynamics Analysis for Asymmetric Power Generation in a Prismatic Fuel Block of Fluoride Salt Cooled High Temperature Test Reactor
(The American Society of Mechanical Engineers (ASME), 2015)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 ... -
Professor Geoffrey Hewitt on His 80th Birthday
(The American Society of Mechanical Engineers (ASME), 2015)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 ... -
Editorial
(The American Society of Mechanical Engineers (ASME), 2015)The Journal of Nuclear Engineering and Radiation Science is an exciting new venture established this year by the ASME with the support and sponsorship of the Nuclear Engineering Division (NED) of the Society. For many ... -
NED Chair’s Message
(The American Society of Mechanical Engineers (ASME), 2015)This inaugural issue of the ASME Journal of Nuclear Engineering and Radiation Science marks a milestone in the history of the ASME Nuclear Engineering Division (NED) currently celebrating its 60th anniversary. As Chair of ... -
Numerical Study of High Temperature and High Velocity Gaseous Hydrogen Flow in a Cooling Channel of a Nuclear Thermal Rocket Core
(The American Society of Mechanical Engineers (ASME), 2015)Two mathematical models (a onedimensional (1D) and a twodimensional (2D)) were adopted to study, numerically, the thermalhydrodynamic characteristics of flow inside the cooling channels of a nuclear thermal rocket (NTR) ...