Journal of Nuclear Engineering and Radiation Science: Recent submissions
Now showing items 841-860 of 913
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Temperature Distribution Inside Fresh Fuel Pins of Pressure Tube Supercritical Water Cooled Reactor
(The American Society of Mechanical Engineers (ASME), 2016)The radial temperature profile for ThO2PuO2 freshfuel pins of the pressuretube supercriticalwatercooled reactor (PTSCWR) is simulated for two different radial distributions of the ThO2 and PuO2, one whereby the ThO2 and ... -
Computational Fluid Dynamics Prediction of Heat Transfer in Rod Bundles With Water at Supercritical Pressure
(The American Society of Mechanical Engineers (ASME), 2016)The paper further explores the application of computational fluid dynamics (CFD) codes for the study of the heattransfer phenomena involved when working with fluids at supercritical pressure; bundle analysis is considered ... -
Axial Power and Coolant Temperature Profiles for a Non Re Entrant Pressure Tube Supercritical Water Cooled Reactor Fuel Channel
(The American Society of Mechanical Engineers (ASME), 2016)The axial power and coolanttemperature distributions in a fuel channel of the Generation IV pressuretube supercritical watercooled reactor (PTSCWR) are found using coupled neutronicsthermalhydraulics calculations. The ... -
Effect of Oxidation Chemistry of Supercritical Water on Stress Corrosion Cracking of Austenitic Steels
(The American Society of Mechanical Engineers (ASME), 2016)Austenitic steel is a candidate material for supercritical watercooled reactor (SCWR). This study is to investigate the stress corrosion cracking (SCC) behavior of HR3C under the effect of supercritical water chemistry. A ... -
Effect of Thermal Pretreatment on the Corrosion of Stainless Steel in Flowing Supercritical Water
(The American Society of Mechanical Engineers (ASME), 2016)The effect of hightemperature microstructure degradation (thermal ageing) on the corrosion resistance of austenitic stainless steels in supercritical water (SCW) was evaluated in this study. Millannealed (MA) and thermally ... -
Oxidation Parameters of Oxide Dispersion Strengthened Steels in Supercritical Water
(The American Society of Mechanical Engineers (ASME), 2016)The kinetic parameters of oxidation of two oxide dispersion strengthened (ODS) alloys, PM2000 and MA956, in supercritical water (SCW) are evaluated using an updated model that assumes that the growth of the outer layer is ... -
Microstructural Effects on the Oxidation Behavior of Alloy 800HT in Supercritical Water
(The American Society of Mechanical Engineers (ASME), 2016)Alloy 800HT is one promising candidate for use as a fuel cladding material in supercritical watercooled rectors. In the present study, specific thermomechanical processing (TMP) was used to study the effects of grain size ... -
Methodology to Design Simulated Irradiated Fuel by Maximizing Integral Indices (ck, E, G)
(The American Society of Mechanical Engineers (ASME), 2016)Critical experiments are used for validation of reactor physics codes, in particular, to determine the biases and uncertainties in code predictions. To reflect all conditions present in operating reactors, plans for such ... -
Combined Effect of Irradiation, Temperature, and Water Coolant Flow on Corrosion of Zr , Ni–Cr , and Fe–Cr Based Alloys
(The American Society of Mechanical Engineers (ASME), 2016)Investigation of the role of irradiation on the corrosion resistance of structural alloys is of vital importance for selection of supercritical watercooled reactor (SCWR) materials. Gamma heating under SCWR conditions, ... -
Analysis of the Core Exit Temperature and the Peak Cladding Temperature During a SBLOCA: Application to a Scaled Up Model
(The American Society of Mechanical Engineers (ASME), 2016)During lossofcoolant accidents (LOCAs), operators may start accident management (AM) actions when the core exit temperature (CET) measured by thermocouples exceeds a certain value. However, a significant time delay and ... -
Control Rod Withdrawal Analysis of the Supercritical Water Reactor Fuel Qualification Test Facility in the LVR 15 Research Reactor
(The American Society of Mechanical Engineers (ASME), 2016)The aim of the supercritical water reactorfuel qualification test (SCWRFQT) EuratomChina collaborative project is to design an experimental facility for qualification of fuel for the supercritical watercooled reactor. The ... -
European Project “Supercritical Water Reactor–Fuel Qualification Testâ€: Overview, Results, Lessons Learned, and Future Outlook
(The American Society of Mechanical Engineers (ASME), 2016)The supercritical water reactor (SCWR) is one of the six reactor concepts being investigated under the framework of the Generation IV International Forum (GIF). One of the major challenges in the development of a SCWR is ... -
Radiolysis of Supercritical Water at 400آ°C: A Sensitivity Study of the Density Dependence of the Yield of Hydrated Electrons on the (eaq−+eaq−) Reaction Rate Constant
(The American Society of Mechanical Engineers (ASME), 2016)The temperature dependence of the rate constant (k) of the bimolecular reaction of two hydrated electrons (eaq−) measured in alkaline water exhibits an abrupt drop between 150آ°C and 200آ°C; above 250آ°C, it is too small ... -
Sensitivity Studies of Shear Stress Transport Turbulence Model Parameters on the Prediction of Seven Rod Bundle Benchmark Experiments
(The American Society of Mechanical Engineers (ASME), 2016)This paper reports the findings of a sensitivity study of parameters in the shear stress transport (SST) turbulence model in a commercial computational fluid dynamics (CFD) code to predict an experiment from the Generation ... -
Combined Effect of Irradiation and Temperature on the Mechanical Strength of Inconel 800H and AISI 310 Alloys for In Core Components of a Gen IV SCWR
(The American Society of Mechanical Engineers (ASME), 2016)Inconel 800H and AISI 310 alloy samples were exposed to Fe4+ ions to simulate neutron irradiation damage, and then annealed at 400آ°C and 500آ°C to study the kinetics of thermal recovery of the irradiation damage. The ... -
Monte Carlo Simulation of Inclined Reactivity Control Rod and Boron Poisoning for the Canadian SCWR Supercell
(The American Society of Mechanical Engineers (ASME), 2016)The CanadianSCWR is a heavywater moderated supercritical lightwatercooled pressure tube reactor. It is fueled with CANada deuterium uranium (CANDU)type bundles (62 elements) containing a mixture of thorium and plutonium ... -
Expected Safety Performance of the Supercritical Water Reactor Fuel Qualification Test
(The American Society of Mechanical Engineers (ASME), 2016)The supercritical water reactor (SCWR) fuel qualification test is an inpile test of a fourrod fuel assembly at supercritical pressure inside a research reactor, which is operated at atmospheric pressure. The risk of ... -
Irradiation Capabilities at the Halden Reactor and Testing Possibilities Under Supercritical Water Conditions
(The American Society of Mechanical Engineers (ASME), 2016)Different types of instruments have been developed both for inpile fuel and materials studies at the Halden Reactor Project. In recent years, several of the standard instruments have been upgraded to be able to tolerate ... -
Design of an In Pile SCWR Fuel Qualification Test Loop
(The American Society of Mechanical Engineers (ASME), 2016)In the development of the supercritical watercooled reactor (SCWR), an inpile fuel assembly test loop has been designed within the framework of the joint Chinese–European project, called SCWRFQT (Fuel Qualification Test). ... -
Fuel Assembly Design for Supercritical Water Cooled Reactor
(The American Society of Mechanical Engineers (ASME), 2016)The supercritical watercooled reactor (SWCR) has been selected as one of the most promising reactors for Generation IV nuclear reactors due to its higher thermal efficiency and more simplified structure compared to the ...