Search
CSV
RISAnalyses of Simple and Intercooled Recuperated Direct Brayton Helium Gas Turbine Cycles for Generation IV Reactor Power Plants
Publisher: The American Society of Mechanical Engineers (ASME)
Abstract: As a nongreenhouse gas-emitting source, the benefits of nuclear as a main power-generation alternative are yet to be fully explored; part of the reason is due to the significant implementation costs. However, with cycle ...
A Review of the Turbine Cooling Fraction for Very High Turbine Entry Temperature Helium Gas Turbine Cycles for Generation IV Reactor Power Plants
Publisher: The American Society of Mechanical Engineers (ASME)
Abstract: The potential for high turbine entry temperature (TETs) turbines for nuclear power plants (NPPs) requires improved materials and sophisticated cooling. Cooling is critical for maintaining mechanical integrity of the turbine ...
Analyses of the Control System Strategies and Methodology for Part Power Control of the Simple and Intercooled Recuperated Brayton Helium Gas Turbine Cycles for Generation IV Nuclear Power Plants
Publisher: The American Society of Mechanical Engineers (ASME)
Abstract: An important requirement for Generation IV Nuclear Power Plant (NPP) design is the control system, which enables part power operability. The choices of control system methods must ensure variation of load without severe ...
Analyses of the Load Following Capabilities of Brayton Helium Gas Turbine Cycles for Generation IV Nuclear Power Plants
Publisher: The American Society of Mechanical Engineers (ASME)
Abstract: The control system for generation IV nuclear power plant (NPP) design must ensure load variation when changes to critical parameters affect grid demand, plant efficiency, and component integrity. The objective of this study ...
Analyses of a High Pressure Ratio Intercooled Direct Brayton Helium Gas Turbine Cycle for Generation IV Reactor Power Plants
Publisher: The American Society of Mechanical Engineers (ASME)
Abstract: The intercooled cycle (IC) as an alternative to the simple cycle recuperated (SCR) and intercooled cycle recuperated (ICR) is yet to be fully analyzed for the purpose of assessing its viability for utilization within ...
Analyses of Long-Term Off-Design Performance Strategy and Operation of a High-Pressure Ratio Intercooled Brayton Helium Gas Turbine Cycle for Generation IV Nuclear Power Plants
Publisher: The American Society of Mechanical Engineers (ASME)
Abstract: The intercooled cycle (IC) is a simplified novel proposal for generation IV nuclear power plants (NPP) based on studies demonstrating efficiencies of over 45%. As an alternative to the simple cycle recuperated (SCR) and ...
Analyses of the Costs Associated With Very High Turbine Entry Temperatures in Helium Recuperated Gas Turbine Cycles for Generation IV Nuclear Power Plants
Publisher: The American Society of Mechanical Engineers (ASME)
Abstract: Previous analyses of generation IV (GEN IV) helium gas turbine cycles indicated the possibility for high turbine entry temperatures (TETs) up to 1200 °C in order to improve cycle efficiency, using improved turbine blade ...