Journal of Nuclear Engineering and Radiation Science: Recent submissions
Now showing items 881-900 of 913
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Observations in Changes of Electrical Properties in Thermally Neutron Exposed Boron Doped Silicon Semiconductors
(The American Society of Mechanical Engineers (ASME), 2015)Borondoped resistors and transistors were developed using various levels of boron concentration. These were exposed to a thermal neutron flux of about 2أ—108  s−1 cm−2 at various fluences, at Los Alamos National ... -
A Control Oriented Modeling Approach to Spatial Neutronics Simulation of a Lead Cooled Fast Reactor
(The American Society of Mechanical Engineers (ASME), 2015)The most diffused neutronics modeling approach in controloriented simulators is pointwise kinetics. In the framework of developing control strategies for innovative reactor concepts, such a simplified description is less ... -
Assessment of Weld Residual Stress Measurement Precision: Mock Up Design and Results for the Contour Method
(The American Society of Mechanical Engineers (ASME), 2015)Recent experimental work has shown residual stress measurements in welded material to be difficult. To better assess the precision of residual stress measurement techniques, a measurement article was designed to allow ... -
Cross Section Influence on Monte Carlo Based Burn Up Codes Applied to a GFR Like Configuration
(The American Society of Mechanical Engineers (ASME), 2015)This paper reports the results of a comparison among JEFF and ENDF/B data sets when used by SERPENT and MONTEBURNS codes on a gascooled fast reactor (GFR)like configuration. Particularly, it shows a comparison between the ... -
Multifragmentation Markov Modeling of a Reactor Trip System
(The American Society of Mechanical Engineers (ASME), 2015)Markov models (MM) are widely used in dependability assessment of complex safetycritical systems. The main computational difficulties in using MMs are model size and stiffness. Selection of the solution approach (SA) and ... -
High Efficiency Gamma Beta Blind Alpha Spectrometry for Nuclear Energy Applications
(The American Society of Mechanical Engineers (ASME), 2015)A novel, centrifugally tensioned metastable fluid detector (CTMFD) sensor technology has been developed over the last decade to demonstrate high selective sensitivity and detection efficiency to various forms of radiation ... -
Nuclear Energy Needs a Turning Point Soon
(The American Society of Mechanical Engineers (ASME), 2015)Figureآ 1 shows the past and potential future of the U.S. nuclear power generation [1]. In the 1970s to 1990s, we were building nuclear power plants and reached roughly 19% nuclear power of the entire electric power demand. ... -
Investigation of Buoyancy Effects on Heat Transfer Characteristics of Supercritical Carbon Dioxide in Heating Mode
(The American Society of Mechanical Engineers (ASME), 2015)Experiments were performed to investigate the effects of buoyancy on heat transfer characteristics of supercritical carbon dioxide in heating mode. Turbulent flows with Reynolds numbers up to 60,000, at operating pressures ... -
Noncontact Measurement Method of Vibration Stress Using Optical Displacement Sensors for Piping Systems in Nuclear Power Plants
(The American Society of Mechanical Engineers (ASME), 2015)In nuclear power plants, vibration stress of piping is frequently measured to prevent the occurrence of fatigue failure. A simpler and more efficient measurement method is desired for rapid integrity evaluation of piping. ... -
Thermodynamics of Nuclear Waste Reprocessing: Separation of Lanthanides Using Liquid Metals and Alloys
(The American Society of Mechanical Engineers (ASME), 2015)Thermodynamics of separation of praseodymium and neodymium employing liquid lowmelting metals and alloys is considered. Pr/Nd separation factors on liquid Ga, In, Bi, and GaIn eutectic were calculated from the thermodynamic ... -
Analysis of Focusing Effect of Light Metallic Layer in Stratified Molten Pool Under IVR ERVC Condition
(The American Society of Mechanical Engineers (ASME), 2015)The main failure mechanism of invessel corium retention through external reactor vessel cooling (IVRERVC) happens when the local heat flux through reactor pressure vessel (PRV) wall exceeds the critical heat flux (CHF). ... -
Thermal Hydraulic and Neutronic Analysis of a Reentrant Fuel Channel Design for Pressure Channel Supercritical Water Cooled Reactors
(The American Society of Mechanical Engineers (ASME), 2015)To address the need to develop new nuclear reactors with higher thermal efficiency, a group of countries, including Canada, have initiated an international collaboration to develop the next generation of nuclear reactors ... -
Calculations and Measurements of Pressure Vessel Thermal Neutron Fluxes in the VVER 1000 Mock Up in the LR 0 Research Reactor
(The American Society of Mechanical Engineers (ASME), 2015)This paper deals with measured as well as calculated parameters of thermal neutron transport in the reactor pressure vessel model, located behind the LR0 reactor vessel. A VVER1000 mockup core placed in the LR0 reactor is ... -
Characterization of Incandescent Particles Emitted by a Cut Off Grinder During Decommissioning Operations for Evaluating Filter Degradation
(The American Society of Mechanical Engineers (ASME), 2015)The use of mechanical or thermal cutting tools when decommissioning nuclear facilities generates a lot of incandescent particles. These particles may represent a deterioration risk of the containment barriers associated ... -
Power Cycles of Generation III and III+ Nuclear Power Plants
(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, and standard of living. In general, electrical energy can be generated by (1)آ nonrenewable energy sources such as ... -
Enhancing Numerical Stability of a Two Fluid Model by the Use of Interfacial Pressure Terms
(The American Society of Mechanical Engineers (ASME), 2015)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 ... -
A Physically Based, One Dimensional Two Fluid Model for Direct Contact Condensation of Steam Jets Submerged in Subcooled Water
(The American Society of Mechanical Engineers (ASME), 2015)A simulation model for the direct contact condensation of steam in subcooled water is presented that allows determination of major parameters of the process, such as the jet penetration length. Entrainment of water by the ... -
Simulation of Supercritical CO2 Flow Through Circular and Annular Orifice
(The American Society of Mechanical Engineers (ASME), 2015)Supercritical CO2 (sCO2) is a promising working fluid for future highefficiency power conversion cycles. In order to develop these cycles, it is necessary to understand supercritical and twophase CO2 flow. This paper ... -
Experimental Observations on Wake Characteristics of a Rising Bubble in a Vertical Narrow Rectangular Channel
(The American Society of Mechanical Engineers (ASME), 2015)Wake characteristics of a rising air and vapor bubble through stagnant and flowing deionized water in a vertical narrow rectangular channel were investigated using particle image velocimetry (PIV). Influence of inlet average ... -
Study on Neutronics and Thermalhydraulics Characteristics of 1200 MWel Pressure Channel Supercritical Water Cooled Reactor
(The American Society of Mechanical Engineers (ASME), 2015)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 ...