5 research outputs found
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SUPERH-SG, a computer model describing nonequilibrium, two phase flow in a light water reactor steam generator during reflood
An existing computer model for emergency core cooling reflood heat transfer has been modified to describe the nonequilibrium, two-phase, thermal-hydraulic pheonomena in a double-pass steam generator of a light water reactor during reflood. The predictive quality of the model has been assessed by comparison of calculated results with temperature, quality, and heat transfer data from an experiment which simulated the thermal-hydraulic performance of a pressurized water reactor steam generator. The calculated temperatures and qualities are generally within the experimental data uncertainty for a wide range of test conditions. Calculated heat transfer is less well calculated, but adequate for many purposes
Turning MOOCS around: Increasing undergraduate academic performance by reducing test-anxiety in a flipped classroom setting
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Fundamental Thermal Fluid Physics of High Temperature Flows in Advanced Reactor Systems - Nuclear Energy Research Initiative Program Interoffice Work Order (IWO) MSF99-0254 Final Report for Period 1 August 1999 to 31 December 2002
The ultimate goal of the study is the improvement of predictive methods for safety analyses and design of advanced reactors for higher efficiency and enhanced safety and for deployable reactors for electrical power generation, process heat utilization and hydrogen generation. While key applications would be advanced gas-cooled reactors (AGCRs) using the closed Brayton cycle (CBC) for higher efficiency (such as the proposed Gas Turbine - Modular Helium Reactor (GT-MHR) of General Atomics [Neylan and Simon, 1996]), results of the proposed research should also be valuable in reactor systems with supercritical flow or superheated vapors, e.g., steam. Higher efficiency leads to lower cost/kwh and reduces life-cycle impacts of radioactive waste (by reducing waters/kwh). The outcome will also be useful for some space power and propulsion concepts and for some fusion reactor concepts as side benefits, but they are not the thrusts of the investigation. The objective of the project is to provide fundamental thermal fluid physics knowledge and measurements necessary for the development of the improved methods for the applications