Journal of Nuclear Engineering and Radiation Science: Recent submissions
Now showing items 821-840 of 913
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Special Issue: Seventh International Symposium on Supercritical Water Cooled Reactors
(The American Society of Mechanical Engineers (ASME), 2016)This special issue of the Journal of Nuclear Engineering and Radiation Science features selected papers from the 7th International Symposium on Supercritical WaterCooled Reactors (ISSCWR7), held from March 15 to 18, 2015, ... -
TRICO II Core Inventory Calculation and its Radiological Consequence Analyses
(The American Society of Mechanical Engineers (ASME), 2016)Two severe accident scenarios are investigated in this paper as they have never been considered previously in the safety analysis report (SAR) of the Congo TRIGA Mark II research reactor (TRICO II) in Kinshasa, the Democratic ... -
Application of Thermal Hydraulic and Severe Accident Code SOCRAT/V3 to Bottom Water Reflood Experiment QUENCH LOCA 1
(The American Society of Mechanical Engineers (ASME), 2016)This study aims to (1)آ use the thermal hydraulic and severe fuel damage (SFD) bestestimate computer modeling code SOCRAT/V3 for posttest calculation of QUENCHLOCA1 experiment and (2)آ estimate the SOCRAT code quality of ... -
Numerical Study of Fluid–Structure Interaction With Heat Transfer at Supercritical Pressure in a Fuel Rod Assembly
(The American Society of Mechanical Engineers (ASME), 2016)Irregular temperature profiles inside nuclear reactors cause the deformation of fuel rods. Due to difficulties in implementing this phenomenon, it is usually neglected in computational fluid dynamics (CFD) analyses. ... -
Oxidation Behavior of Austenitic Stainless Steel 316L and 310S in Air and Supercritical Water
(The American Society of Mechanical Engineers (ASME), 2016)In this study, we evaluated the oxidation resistance of austenitic stainless steels 316L and 310S in two different environments: air at 600آ°C and atmospheric pressure and supercritical water at 600آ°C and pressure of ... -
Experimental Heat Transfer in an Annular Channel and 3 Rod Bundle Cooled With Upward Flow of Supercritical Water
(The American Society of Mechanical Engineers (ASME), 2016)There have been relatively few publications detailing heat transfer to supercritical water (SCW) flowing through a channel with a bundle or just with a single rod (annular channel) as compared to heat transfer to SCW in ... -
Effect of Surface Oxidation on the Onset of Nucleate Boiling in a Materials Test Reactor Coolant Channel
(The American Society of Mechanical Engineers (ASME), 2016)The onset of nucleate boiling (ONB) serves as the thermalhydraulic operating limit for many research and test reactors. However, boiling incipience under forced convection has not been wellcharacterized in narrow channel ... -
Assessment of Candidate Fuel Cladding Alloys for the Canadian Supercritical Water Cooled Reactor Concept
(The American Society of Mechanical Engineers (ASME), 2016)Selecting and qualifying a fuel cladding material for the Canadian supercritical watercooled reactor (SCWR) concept remains the most significant materials challenge to be overcome. The peak cladding temperature in the ... -
Mitigating the Stress Corrosion Cracking of Zircaloy 4 Fuel Sheathing: Siloxane Coatings Revisited
(The American Society of Mechanical Engineers (ASME), 2016)For more than 50آ years, a thin (3–20آ خ¼m) graphite coating has played an important role in limiting the stress corrosion cracking (SCC) of Zircaloy4 fuel sheathing in CANDUآ® nuclear reactors. Siloxane coatings, which ... -
Analysis of Thermal Hydraulic Fluctuations in Trillo NPP With CTF/PARCS v. 2.7 Coupled Code
(The American Society of Mechanical Engineers (ASME), 2016)The lowfrequency noises are fluctuations in the neutron flux density, in the lowfrequency range up to 4آ Hz, which generate noise in the neutron instrumentation and could affect the limitation and protection system of the ... -
Iodine Benchmarks in the SARNET Network of Excellence
(The American Society of Mechanical Engineers (ASME), 2016)Accurate calculation of iodine behavior in the containment is very important in determining the potential radioactive release to the environment in light water reactor severe accidents (SAs). Of particular significance is ... -
Screening and Correlating Data on Heat Transfer to Fluids at Supercritical Pressure
(The American Society of Mechanical Engineers (ASME), 2016)A simple criterion for screening experimental data on turbulent heat transfer in vertical tubes to identify those not significantly influenced by buoyancy was proposed by the author many years ago and found to work quite ... -
Assessment of Computational Tools in Support of Heat Transfer Correlation Development for Fuel Assembly of Canadian Supercritical Water Cooled Reactor
(The American Society of Mechanical Engineers (ASME), 2016)Experimental data and correlations are not available for the fuelassembly concept of the Canadian supercritical watercooled reactor (SCWR). To facilitate the safety analyses, a strategy for developing a heattransfer ... -
Fission Product Release Under Supercritical Water Cooled Reactor Conditions
(The American Society of Mechanical Engineers (ASME), 2016)Most supercritical watercooled reactor (SCWR) concepts being considered as part of the Generation IV initiative are direct cycle. In the event of a fuel defect, the coolant will contact the fuel pellet, potentially releasing ... -
Oxidation Performance Coating for Future Supercritical Power Plants
(The American Society of Mechanical Engineers (ASME), 2016)For improved efficiency and reduced emissions, the future power plants need to operate at high temperatures and pressures, which however are limited by the durability of conventional materials such as ferritic steels. Steam ... -
Uncertainty Quantification of the RELAP5 Interfacial Friction Model in the Rod Bundle Geometry
(The American Society of Mechanical Engineers (ASME), 2016)Interfacial friction in the core affects the twophase mixture level and the distribution of the dispersed gas phase during a smallbreak lossofcoolant accident (LOCA). The RELAP5/MOD3.2 code uses the drift flux model to ... -
Various Design Aspects of the Canadian Supercritical Water Cooled Reactor Core
(The American Society of Mechanical Engineers (ASME), 2016)The Canadian Supercritical WaterCooled Reactor (SCWR) is a 1200آ MW(e) channeltype nuclear reactor. The reactor core includes 336 vertical pressurized fuel channels immersed in a lowpressure heavy water moderator and ... -
Supercritical Oxidation of Boiler Tube Materials
(The American Society of Mechanical Engineers (ASME), 2016)The advantage of using supercritical water (SCW) systems for power generation is based on the increased thermodynamic efficiency when operating at higher temperature and pressure. Steam oxidation has become an important ... -
Performance of Chemical Vapor Deposition and Plasma Spray Coated Stainless Steel 310 in Supercritical Water
(The American Society of Mechanical Engineers (ASME), 2016)In this study, aluminized and NiCrAlY plasmasprayed AISI 310 stainless steel samples were tested in supercritical water (SCW) at 500آ°C. The microstructure after SCW exposure was analyzed using scanning electron microscopy ... -
Steady State Radiolysis of Supercritical Water: Model Predictions and Validation
(The American Society of Mechanical Engineers (ASME), 2016)Chemical kinetic models are being developed for the خ³radiolysis of subcritical and supercritical water (SCW) to estimate the concentrations of radiolytically produced oxidants. Many of the physical properties of water ...