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 the intercooled cycle recuperated (ICR), the main difference in configuration is no recuperator, which reduces its size. It is expected that the components of the IC will not operate at optimum part power due to seasonal changes in ambient temperature and grid prioritization for renewable sources. Thus, the ability to demonstrate viable part load performance becomes an important requirement. The main objective of this study is to derive off-design points (ODPs) for a temperature range of −35 °C to 50 °C and core outlet temperatures (COTs) between 750 °C and 1000 °C. The ODPs have been calculated using a tool designed for this study. Based on the results, the intercooler changes the mass flow rate and compressor pressure ratio (PR). However, a drop of ∼9% in plant efficiency, in comparison to the ICR (6%) was observed for pressure losses of up to 5%. The reactor pressure losses for IC have the lowest effect on plant cycle efficiency in comparison to the SCR and ICR. Characteristic maps are created to support first-order calculations. It is also proposed to consider the intercooler pressure loss as a handle for ODP performance. The analyses brings attention to the IC an alternative cycle and aids development of cycles for generation IV NPPs specifically gas-cooled fast reactors (GFRs) and very-high-temperature reactors (VHTRs), using helium.
Highlights
A simplified configuration and an efficient cycle for Nuclear Power Plants (NPPs) are necessary for Generation IV (Gen IV) development in order to deliver low cost NPPs [1]
It is expected that the components of the Intercooled Cycle (IC) will not operate at optimum part power
calculated using a tool designed for this study
Summary
A simplified configuration and an efficient cycle for Nuclear Power Plants (NPPs) are necessary for Generation IV (Gen IV) development in order to deliver low cost NPPs [1]. Beyond deriving better plant efficiencies at Design Point (DP), the Off-Design Point (ODP) is just as critical to ensure the plant runs efficiently for long term periods when ambient conditions change and grid prioritisations are in favour of renewable sources. This is challenging because the coupled individual components limit the amount of optimum ODPs that the plant can run at [3]; finding these ODPs require very complex iterative calculations. The cycle of interest is the IC, with comparisons to a similar study (Ref [6]) of the Intercooled Cycle Recuperated (ICR) and the Simple Cycle Recuperated (SCR)
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More From: Journal of Nuclear Engineering and Radiation Science
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